ABSTRACTS - ena-norm.eu3) radon exhalation rate from soil using for radon map in cluj city, romania - mócsy ildikó, néda tamás, hening kinga..... 17 4) a comparative analysis of

NORM IV Conference May 2004, Szczyrk POLAND

ABSTRACTS

1) IMPLEMENTATION OF THE EUROPEAN DIREC-TIVE 96/29/EURATOM IN IRELAND – STATUS OFCURRENT INVESTIGATIONS - Catherine Organo ...................... 13

2) INVESTIGATION OF THE PEAT-FIRED POWERGENERATION IN IRELAND - Catherine Organo,

Elaine Lee, Gerard Menezes, Eric Finch ...................... 15

3) RADON EXHALATION RATE FROM SOIL USINGFOR RADON MAP IN CLUJ CITY, ROMANIA -

Mócsy Ildikó, Néda Tamás, Hening Kinga ...................... 17

4) A COMPARATIVE ANALYSIS OF THE HEAVYMETALS, HEAVY NATURAL RADIONUCLIDES

CONCENTRATIONS AND BIOINDICATION ASSAYOF WATER SAMPLED FROM A RADIUM PRO-

DUCTION INDUSTRY STORAGE CELL TERRITO-RY - T. Evseeva, S. Geras’kin, Shuktomova I., A.

Taskaev ...................... 19

5) A COMPARATIVE ANALYSIS OF BIOLOGICAL EF-FECTS IN PLANTS INHABITING TWO RUSSIAN

REGIONS WITH A HIGHER LEVEL OF HEAVYNATURAL RADIONUCLIDES - S. Geras’kin, T.

Evseeva, A. Taskaev, I. Shuktomova ...................... 21

6) EXPOSURE FROM AN IGNEOUS PHOSPHATEMINE OPERATION - A.J. vd Westhuizen, Foskor ...................... 23

7) RADIOLOGICAL RISK ASSESSMENT OF PHOS-PHOGYPSUM PLASTERBOARDS IN HOMES -

A.J. vd Westhuizen, G.P. de Beer, Foskor ...................... 25

8) RAIL TRANSPORT OF IGNEOUS PHOSPHATEROCK - A.J. vd Westhuizen, G.P. de Beer ...................... 27

Page 1 of 199


9) NORM IN BUILDING MATERIALS - Aliyev Chingiz ...................... 28

10) NORM IN COAL - T.A. Zolotovitskaya ...................... 30

11) RADIONUCLIDE CONTAMINATION OF THE NAT-URAL ENVIRONMENT OF ABSHERON PENINSU-

LA (AZERBAIJAN) - Sabina Aliyeva ...................... 32

12) MITIGATION METHODS IN SELECTION PLACESOF CONSTRUCTION SITES - Aliyev Chingiz,

Tamara Zolotovitskaya, Sabina Aliyeva ...................... 34

13) NATURAL RADIONUCLIDES IN RARE EARTH IN-DUSTRY AND THEIR ENVIRONMENTAL EF-

FECTS - Xiaolin Hou, Weiyue Feng ...................... 36

14) CRYING WOLF! HOW TO DEAL WITH PRE-SUMED RADIOACTIVE CONTAMINATION - Heldio

P. Villar, Carlos de Austerlitz Campos ...................... 38

15) ENVIRONMENTAL RADIOLOGICAL IMPACT BY AFERTILIZER COMPLEX

IN THE EBRO RIVER (SPAIN) - E. Costa1), J.A.Sanchez-Cabeza, J. Garcia, P. Masqué, J.O.

Grimaltb ...................... 40

16) ASSESSMENT OF NORM IN SAUDI ARAMCO FA-CILITIES - Khalid Mously, Osama Fageeha, Michael

Cowie ...................... 42

17) THE 238U–234TH EQUILIBRIUM IN SOIL SAMPLES -D. Mrđa, I. Bikit, J. Slivka, M. Vesković, Lj. Čonkić,

N. Todorović, E. Varga, S. Ćurčić ...................... 43

18) RADIOACTIVITY OF THE FOOD AT NOVI SADMARKETS - Ester Z. Varga, Ištvan S. Bikit, Jaroslav

M. Slivka, Nataša M. Žikić-Todorović, Miroslav J.Vesković, Ljiljana U. Čonkić, Dušan S. Mrđa ...................... 44

Page 2 of 199


19) NATURAL RESTORATION OF A SPANISH ESTU-ARY HISTORICALLY AFFECTED BY ANTHRO-

POGENIC INPUTS OF NATURAL RADIONU-CLIDES - M. Villa, A. Absi, H. P. Moreno, R. García-

Tenorio, G. Manjón ...................... 45

20) TENORM REGULATORY FRAMEWORK INBRAZIL - Horst Fernandes, Mariza Franklin, Monica

Pires do Rio ...................... 47

21) THE FIRST RADON MAP OF VOJVODINA - S.Ćurčić, I. Bikit, Lj. Čonkić, M. Vesković, J. Slivka, Lj.

Čonkić, E. Varga, N. Žikić-Todorović, D. Mrđa ...................... 49

22) EVALUATION OF OCCUPATIONAL RADIOLOGI-CAL EXPOSURES ASSOCIATED WITH FLY ASH-

ES FROM FRENCH COAL POWER PLANTS -Jean-Pierre Degrange, Samuel Lepicard ...................... 51

23) RECYCLING OF 232TH CONTAMINATED TUNG-STEN SCRAP - U. Quade, W. Müller ...................... 53

24) ON THE MEASUREMENT OF 40K IN NATURALAND SYNTHETIC MATERIALS BY THE METHOD

OF HIGH-RESOLUTION GAMMA-RAY SPEC-TROMETRY - N. Lavi, F. Groppi, Z.B. Alfassi ...................... 55

25) SOIL CONTAMINATION IN A RURAL SITE USEDFOR RARE EARTH INDUSTRY

BY-PRODUCT DISPOSAL - C. Briquet, D. Lauria ...................... 57

26) PASSIVE ANTINEUTRINO SOUNDING OF SPA-TIAL DISTRIBUTION OF RADIOACTIVE ELE-

MENTS IN THE EARTH DEPTHS - V.D. Rusov,V.M. Pavlovich, V.M. Vaschenko ...................... 59

Page 3 of 199


27) STATUS OF RADON DOSIMETRY IN ZAMBIANUNDERGROUND MINES - P. Hayumbu1, S.

Mulenga, M. Nomai, P. Mulenga, R. Katebe, P.Shaba, T. Chunga, D. Inambao, F. Mangala, P.

Tembo, Y. Malama ...................... 61

28) THE RADON DOSEMETER COMBINING CHAR-COAL CANISTERS AND TLD DETECTORS TYPE

MCP-N (LiF: Mg, Cu, P) - Joanna Bogacz, MaciejBudzanowski, Ryszard Haber ...................... 63

29) NORM AND DECOMMISSIONING OF NUCLEARFACILITIES - Kurt Robert Geber ...................... 65

30) IMPORTANCE OF SAMPLING IN RELATION OFTHE GAMMA SPECTROSCOPIC ANALYSES

OF NORM MATERIAL - L.P.M. van Velzen, C.W.M.Timmermans ...................... 66

31) FACTORS CONTROLING MEASUREMENTS OFMASS RADON EXHALATION COEFFICIENT -

Nguyen Dinh Chau, Stefan J. Kalita, Edward Chruś-ciel, Łukasz Prokólski ...................... 68

32) CONCENTRATIONS OF 222Rn IN GROUNDWA-TERS FLOWING THROUGH DIFFERENT CRYS-

TALLINE ROCKS: AN EXAMPLE FROM ŚLĘŻAMASSIF (Poland) - Tadeusz A. Przylibski ...................... 71

33) RADON CHAMBERS – TECHNICAL DESIGN ANDSOME CALIBRATION PROBLEMS - Krzysztof

Kozak, Jadwiga Mazur, Mirosław Janik, TadeuszZdziarski, Ryszard Haber ...................... 73

34) CALIBRATION OF SOIL PROBE FOR IN SITUPERMEABILITY MEASUREMENT - Mirosław Janik,

Krzysztof Kozak ...................... 75

Page 4 of 199


35) INFLUENCE OF METEOROLOGICAL CONDI-TIONS ON RADON MEASUREMENTS IN SOIL –

PRELIMINARY RESULTS - Jadwiga Mazur,Krzysztof Kozak, Tomasz Horwacik, Ryszard Haber,

Tadeusz Zdziarski ...................... 77

36) METHODS FOR ASSESSMENT OF THE OCCU-PATIONAL EXPOSURE AT WORKING PLACES

OF DIFFERENT TENORM INDUSTRIAL BRANCH-ES - Dietmar Weiß, Harald Biesold, Peter Jo-vanovic, Lászlò Juhàsz, Ales Laciok, Karsten

Leopold, Boguslaw Michalik, Hana Moravanská, An-dré Poffijn, Mihail Popescu, Cornel Radulescu, Páv-

el Szerbin, Jens Wiegand ...................... 79

37) DETECTION SYSTEM FOR SURVEY OF THEPROFESIONAL EXPOSED PERSONAL - Ana I.

Stochioiu, Felicia S. Mihai, Iulia I. Georgescu ...................... 81

38) THE PROPOSAL OF THE SWEDISH COMMITTEEON MANAGEMENT OF NON-NUCLEAR RA-

DIOACTIVE WASTE (IKA) AND THE IMPLICA-TIONS FOR THE MANAGEMENT OF NORM ANDSTORAGE OF NORM WASTE - Gustav Åkerblom,

Nils Hagberg, Lars Mjönes, Ann-Louis Söderman ...................... 82

39) SEQUENTIAL EXTRACTION OF URANIUM ISO-TOPES IN SEDIMENTS FROM AN ESTUARY HIS-

TORICALLY AFFECTED BY ANTHROPOGENICINPUTS OF NATURAL RADIONUCLIDES - Juan L.

Aguado1, Juan P. Bolívar, Rafael García-Tenorio ...................... 84

40) ASSESSMENT OF THE RADON CONTRIBUTIONFROM MINING SITES TO

THE GEOGENIC ENVIRONMENT - R. Rolle ...................... 86

41) NEW REGULATORY DEVELOPMENTS ANDGUIDANCE IN THE EU WITH REGARD TO NORM

- T.P. Ryan, A. Janssens, E. Henrich, J.L. Daroussin ...................... 88

Page 5 of 199


42) INDUSTRIES GIVING RISE TO NORM DIS-CHARGES IN THE EU – A REVIEW - T.P. Ryan, A.

Janssens, E. Henrich, J.L. Daroussin, Z.K. Hillis,E.I.M. Meijne ...................... 90

43) THE RAPID IDENTIFICATION OF NORM DIS-CHARGES REQUIRING REGULATORY CONTROL– A POSSIBLE SCREENING METHODOLOGY - E.

Henrich, A. Janssens, T.P. Ryan, J.L. Daroussin,K.R. Smith, M.Y. Gerchikov ...................... 92

44) POLISH NATIONAL INTERCOMPARISONS OFMEASUREMENT METHODS OF 222RN CONCEN-

TRATION IN WATERS - Tadeusz A. Przylibski, Kali-na Mamont-Cieśla, Olga Stawarz, Barbara Kłos,

Jerzy Dorda, SPI Team ...................... 94

45) APPLICATION OF INTERNATIONAL SAFETYSTANDARDS TO WORK INVOLVING EXPOSURE

TO NATURAL RADIATION - Denis Wymer ...................... 97

46) A SPECIFIC STUDY CONCERNING NORM IN RE-FRACTORIES INDUSTRIES - F. Trotti, C. Zampieri,G. Clauser, M. Facchinelli, D. Desideri, G. Jia, P. In-

nocenzi, R. Ocone ...................... 99

47) GRAIN SIZE IN RADIOMETRIC MEASUREMENTSOF GROUND - V. Gablin ...................... 101

48) TEST THRESHOLDS FOR ASSESSMENT OFPOSSIBLE GROUNDWATER CONTAMINATION

AT SITES CONTAMINATED WITH RADIOACTIVEMATERIALS - Rainer Gellermann, Michael Hahn,

Ulrike Haberlau, Joachim Beetz ...................... 103

49) NATURAL RADIOISOTOPE LEVEL DIFFEREN-TIATION IN ARABLE AND NONCULTIVATED

SOILS AT ŁĘCZNA-WŁODAWA LAKE DISTRICT –A. Komosa, St. Chibowski, J. Solecki, M. Reszka ...................... 105

Page 6 of 199


50) ATTEMPTS ON RADON EXHALATION RATE DE-TERMINATION FROM A WASTE-DUMP AT THEBOGDANKA COAL MINE USING THE PICORAD

DETECTORS - A. Komosa, St. Chibowski, St.Chałupnik ...................... 107

51) DETERMINATION OF 210PO AND 210PB FROM MA-RINE SEDIMENTS - Paula Juntunen, Maria Betti ...................... 109

52) COSMOGENIC 22NA AND 7BE IN GROUND LEVELAIR - Sylwia Grabowska, Jerzy W. Mietelski ...................... 110

53) APPLICATION OF LIQUID SCINTILLATION COUN-TING TECHNIQUE TO GROSS ALPHA, GROSSBETA AND RADON MEASUREMENTS IN POR-

TUGUESE WATERS – I. Lopes, M.J. Madruga, F.P.Carvalho ...................... 112

54) EXAMINING THE NATURAL RADIOACTIVITY OFWATER SOURCES TO EVALUATE THE IMPACT

ON SURROUNDING COMMUNITIES - A. Faanhof,P. Kempster ...................... 114

55) THE UK - K.R. Smith*, S.M. Warner Jones, W.B.Oatway, J.A. Jones, M.P. Harvey, P.V. Shaw, S.F.

Mobbs ...................... 116

56) RADIONUCLIDE CONTAMINATION OF SURFACEWATERS, SEDIMENTS, AND SOIL CAUSED BY

COAL MINING ACTIVITIES IN THE RUHR DIS-TRICT (GERMANY) - Simone Schmid, Jens Wie-

gand ...................... 117

57) PRESENCE OF NORM IN THE CZECH REPUBLIC- H. Moravanska, A. Laciok ...................... 118

58) THE PERIODICAL CHANGES THE CONCENTRA-TION OF INDOOR RADON - Maria Karpińska,

Zenon Mnich, Jacek Kapała ...................... 120

Page 7 of 199


59) INTERCOMPARISON OF INSTRUMENTS FORMEASURING RADON AND RADON PROGENY

HELD IN THE CLOR CALIBRATION CHAMBER -Kalina Mamont-Cieśla, Olga Stawarz (This work was

partially supported by Radon Center.) ...................... 122

60) AEROSOL SAMPLING FOR RADIOLOGICAL PRO-TECTION: WHICH PARTICLE SIZE AEROSOL

SAMPLER TO SELECT? - Jean-Pierre Degrange,Olivier Witschger ...................... 125

61) A PROTOCOL FOR DETERMINATION OF NATU-RAL RADIONUCLIDES IN THE GEOTHERMALWATER - Henryk Bem, Marcin Olszewski, Aneta

Kaczmarek ...................... 127

62) DETERMINATION OF RADIUM 226RA NUCLIDE INGROUND-LEVEL AIR - Henryk Bem, Marcin Ol-

szewski ...................... 129

63) ENVIRONMENTAL RADIOLOGICAL MONITORINGIN A NIOBIUM MINING REGION IN BRAZIL -Marcelo Francis Máduar, Ana Cláudia Peres,

Barbara Paci Mazzilli ...................... 131

64) RADIONUCLIDES IN SWEDISH DRINKING WA-TER - Britt-Marie Ek ...................... 133

65) RELEASE OF NORM-RESIDUES FROM SURVEIL-LANCE IN GERMANY – SOME PRACTICAL EXPE-

RIENCE - Rainer Gellermann ...................... 135

66) IDENTIFICATION OF ENHANCED CONCENTRA-TIONS OF 210PB AND 210PO IN DUST SAMPLESFROM STEEL-WORKS - J. Döring, J. Gerler, M.

Beyermann, U.K. Schkade, J. Freese ...................... 137

Page 8 of 199


67) TEST OF THE MATERIAL FOR RADON SEALLAYER AT THE MINE WASTE DISPOSAL SITE

JAZBEC - Jozef Rojc, Mine Zirovski Vrh ...................... 138

68) ESTIMATION OF RADON DOSE IN SEVERALWORKPLACES USING DOSIMETRIC MODEL FOR

INHALATION OF AIRBORNE RADIONUCLIDES -Kalina Mamont-Cieśla, Olga Stawarz ...................... 140

69) SAMPLE CLEAN-UP BY ON-LINE CHROMATOG-RAPHY FOR THE DETERMINATION OF PU ANDAM IN SEDIMENTS - Jussi Jernström, Maria Betti ...................... 142

70) THE INVENTORY OF ITALIAN NORM CON-CERNED WORK ACTIVITIES IN THE FRAME OF

ENVIRONMENT PROTECTION - F. Trotti, C.Zampieri, S. Bucci, G. Clauser, G. Colombo, D.

Desideri, M. Facchinelli, L. Gaidolfi, G. Torri ...................... 144

71) URANIUM ISOTOPES IN PUBLIC DRINKING WA-TER IN POLAND - Zofia Pietrzak-Flis, Iwona

Kamińska, Edward Chrzanowski ...................... 146

72) CHARACTERISATION OF SCALE FROM A FOR-MER PHOSPHORIC ACID PROCESSING PLANT -

Helen Beddow, Stuart Black, David Read ...................... 148

73) VENTILATION: A TECHNIQUE FOR INDOORRADON MITIGATION - K. Kant, R.P. Chauhan, S.K.

Chakarvarti ...................... 150

74) IN SITU GAMMA-RAY SPECTROMETRY IN COM-MON ROCK RAW MATERIALS MINED IN

KRAKOW VICINITY, POLAND - D. Malczewski, L.Teper, G.Lizurek ...................... 152

Page 9 of 199


75) SOURCES OF TENORM – INVENTORY OF PHOS-PHATE FERTILIZERS AND ALUMINUM INDUS-TRIES - Dan Georgescu, Florian Aurelian, Mihai

Popescu, Cornel Rădulescu ...................... 154

76) RADON MEASUREMENTS AS A MONITORINGPOSSIBILITY FOR MINING SUBSIDENCE OC-

CURRENCES - A.Kies, A. Storoni, Z. Tosheva ...................... 156

77) NATURALLY OCCURING RADIOACTIVE MATERI-AL (NORM) ASSESSMENT OF OIL AND GAS

PRODUCTION INSTALLATIONS IN NIGERIA - S.B.Elegba, I.I. Funtua ...................... 158

78) NATURALLY OCCURRING RADIONUCLIDES INRAW MATERIALS, PRODUCTS AND WASTE INTHE STEEL INDUSTRY - Hanna Firganek, Artur

Żak, Jarosław Marcisz ...................... 160

79) ANALYTICAL METHODS USED FOR DETERMIN-ING NATURAL RADIONUCLIDES IN FINNISH

DRINKING WATER - Pia Vesterbacka, Laina Salo-nen ...................... 163

80) RADIUM LEACHING FROM MINE DEPOSITS AS APOSSIBLE SOURCE

OF GROUNDWATER CONTAMINATION -Stanisław Chałupnik ...................... 165

81) MEASUREMENT OF SHORT-LIVED RADONDAUGHTERS IN POLISH MINES - Krystian Sku-

bacz, Antoni Mielnikow ...................... 167

82) RADIUM REMOVAL FROM MINE WATERS – UN-DERGROUND TREATMENT INSTALLATION - Mał-

gorzata Wysocka, Stanisław Chałupnik, ElżbietaMolenda ...................... 168

Page 10 of 199


83) RADIUM BALANCE IN DISCHARGE WATERSFROM COAL MINESIN UPPER SILESIA REGION -

Stanisław Chałupnik, Małgorzata Wysocka, AntoniMielnikow, Bogusław Michalik, Jan Skowronek ...................... 170

84) THEORETICAL STUDY OF RADIUM BEHAVIOURIN AQUIFERS - Stanisław Chałupnik ...................... 172

85) RADIUM BEHAVIOUR DURING DESALINATIONPROCESSES OF MINE WATERS - Stanisław

Chałupnik, Krystian Skubacz ...................... 174

86) INVESTIGATIONS OF SURFACE SETTLINGPOND - Małgorzata Wysocka, Stanisław Chałupnik ...................... 176

87) RADON IN SOME CAVES OF KRAKOW-CZESTO-CHOWA JURASSIC UPLAND - Jan Skowronek,

Małgorzata Wysocka, Michał Giebel ...................... 178

88) NORM LEGISLATION IN POLAND - Jan Skowronek ...................... 180

89) NORM IN MINING INDUSTRY IN POLAND - JanSkowronek ...................... 181

90) THE ASSESSMENT OF EXPOSURE TO IONIZINGRADIATION AT SPOIL BANKS - Bogusław Michalik ...................... 182

91) RANKING OF TENORMS IMPACT INTO RADIA-TION RISK - Bogusław Michalik ...................... 184

92) TOWARDS A METHODOLOGY FOR IDENTIFYINGNON NUCLEAR SITES

WITH ENHANCED LEVELS OF RADIOACTIVITY -Christian Cosemans, Hans Vanmarcke ...................... 185

Page 11 of 199


93) THE EFFECT OF EARTHQUAKE-INDUCEDRADON RELEASE ON THE POPULATION IN THE

SEISMIC ACTIVE REGIONS OF ARMENIA - E.Saghatelyan, A. Petrosyan, Yu. Aghbalyan, M.

Baburyan, A. Davtyan ...................... 187

94) 210PO AND 210PB IN ENVIRONMENTAL SAMPLESIN FINNISH LAPLAND - Dina Solatie, Kristina

Rissanen ...................... 189

95) NORM IN DRINKING WATER – MEASUREMENTSUSING ULTRA LOW-LEVEL LIQUID

SCINTILLATION SPECTROMETRY ANDCONSIDERATIONS FOR COMPLIANCE WITH

THE EU DRINKING WATER DIRECTIVE - FranzSchönhofer, Franz-Josef Maringer ...................... 191

96) RADIUM IN GROUND WATER CLOSE TO BUENALAGOON IN COASTAL ZONE OF RIO DE

JANEIRO STATE, BRAZIL - Dejanira C. Lauria, Ro-drigo M. R. Almeida, and Ondra Sracek ...................... 193

97) IMPROVING CRITERIA FOR REMEDIATION OFMONAZITE BY-PRODUCTS CONTAMINATED

SITES IN BRAZIL - Briquet, Claudia ; Silva, Katia,M.; Cipriani, M. ...................... 195

98) ENVIRONMENTAL ASSESSMENT OF THE MATE-RIAL DEPOSITED ON THE FORMER URANIUM

MINING DISPOSAL DUMP IN RADONIÓW - A.Żak,M.Biernacka, K. Isajenko, P.Lipiński, K. Posłuszny ...................... 197

Page 12 of 199


IMPLEMENTATION OF THE EUROPEAN DI-RECTIVE 96/29/EURATOM IN IRELAND – STA-

TUS OF CURRENT INVESTIGATIONS

Catherine Organo

Radiological Protection Institute of Ireland, 3 Clonskeagh Square Clonskeagh

Road, Dublin 14, IRELAND,

e-mail: [email protected]

The European Union Basic Safety Standard (BSS) Directive (96/29/EURATOM) is

revised in line with scientific developments approximately every ten to fifteen

years. The most recent revision, which took place in 1996, includes special provi-

sions concerning exposure to natural sources of ionising radiation. Title VII of the

revised Directive sets down a framework for controlling work activities where the

presence of natural radiation sources leads to a significant increase in exposure to

workers or members of the public, which cannot be disregarded from the radiation

protection point of view.

The implementation of Title VII resulted in significant legal changes in Ireland. It

has been incorporated into Irish law by a Ministerial Order (Statutory Instrument

No. 125 of 2000) which came into force in May 2000.

This presentation will review the measures taken and progress achieved so far by

the national regulatory agency, the Radiological Protection Institute of Ireland

(RPII) since the coming into force of the new regulations in Ireland.

Based on their economical significance, a group of three major industries currently

active in Ireland have been investigated from a list of work activities which, on thePage 13 of 199


basis of the literature, were considered liable to involve work practices resulting in

exposure to NORMs. They include: the gas extraction and production industry, the

peat-and coal-firing power generation industry.

For each of them, the RPII made an initial assessment of the scale of the problem

by reviewing existing (non exhaustive) literature. Meetings with the industry re-

spective management responsible for the personnel and/or the Health and Safety

and/or the environment were organised to increase their level of awareness with

regard to the current legislation and discuss of the potential consequences. This

allowed us to compile information characteristic of each case and focus our inter-

est on particular issues.

Field investigations were carried out and monitoring programmes put in place. Re-

sults obtained so far will be presented and preliminary conclusions will be drawn.

Additionally, the bauxite/alumina refining industry (the largest European plant of

this type is located in the West of Ireland), the cement industry and users of titani-

um oxide (pigment industry) and zircon sands are all scheduled to be investigated

from 2004 onward. A brief overview of the radiological issues for each industry will

also be presented.

Page 14 of 199


INVESTIGATION OF THE PEAT-FIRED POW-ER GENERATION IN IRELAND

Catherine Organo1), Elaine Lee2), Gerard Menezes3), Eric Finch3)

1) Radiological Protection Institute of Ireland, 3 Clonskeagh Square,

Clonskeagh Road, Dublin 14, IRELAND


2) Director of Buildings’ Office, West Chapel, Trinity College, Dublin 2,

IRELAND3) Physics Department, Trinity College, Dublin 2, IRELAND

As the national agency with regulatory responsibility for ionising radiation in

charge of the implementation of the most recent version of the BSS Directive

96/29/EURATOM, the Radiological Protection Institute of Ireland (RPII) initiated a

programme in 2000 to identify types of industry currently active in Ireland, which

on the basis of the literature were considered liable to (1) involve operations with

and storage of materials not usually regarded as radioactive but which contain

naturally occurring radionuclides causing a significant increase in the exposure of

workers and, where appropriate, members of the public and/or (2) lead to the pro-

duction of residues not usually regarded as radioactive but which contain naturally

occurring radionuclides causing a significant increase in the exposure of workers

and, where appropriate, members of the public.

Page 15 of 199


Irish industries meeting one or two of the above conditions include the gas extrac-

tion industry, the fossil fuel power production (peat and coal-fired) and industrial

processes using bulk materials with enhanced levels of NORMs (bauxite refinery,

cement industry, mineral sands).

The Irish situation with regard to electricity generation is of particular interest as

approximately 15% of the country’s electricity requirement is provided through

peat combustion. By 2004, only two large power plants will remain operative, rep-

resenting a combined capacity of 250 MW. Between the two of them, just over 2

million tonnes of peat per annum will be used.

At the end of 2001, the RPII initiated a radiological investigation of the largest Irish

peat-fired power plant in collaboration with Trinity College Dublin (TCD) and the

Electricity Supply Board (ESB, the national Irish electricity supplier) to review the

potential occupational exposures arising from the occurrence of NORMs at differ-

ent stages of the industrial process. The objectives were to provide a valuable ex-

perience to the RPII in the frame of the new EU Directive, if necessary to provide

the peat industry with advices and/or guidelines to adapt the production process

and the environmental discharges to the new regulations, and finally to produce

the first comprehensive radiological study of this industry.

Results of field investigations (external radiation dose rate measurements, aerial

radon measurements, inhalation of airborne radioactive particles) and on-going

monitoring of the radioactivity content of the peat, peat ash and effluent samples

from the ash ponds will be presented as well as calculations of estimated radiation

doses to workers involved in relevant work activities.

Page 16 of 199


RADON EXHALATION RATE FROM SOIL US-ING FOR RADON MAP IN CLUJ CITY, ROMA-

NIA

Mócsy Ildikó1), Néda Tamás2), Hening Kinga3)

1) Sapientia University, Faculty of Environmental Sciences, 400462 Cluj-

Napoca, str. Brâncuşi 18/A, ROMANIA,


2) Sapientia University, Faculty of Environmental Sciences, 400064 Cluj-

Napoca, str. Ady Endre 28, , ROMANIA


3) Babes-Bolyai University, Physics Department, 400084 Cluj-Napoca str.

Kogalniceanu 1, ROMANIA

The majority of countries of the Carpathian Basin have no radon map. The goal of

the paper is a proposal for a common sampling and measurement method to esti-

mate the radon potential of this area.

The research was effectuated in 2003 summer and autumn period. The measure-

ment points were chosen taking account the soil characteristics. Different soil

types were investigated. The soil radon gas concentration was measured using

track-etched detectors and the radon exhalation from soil was determined with ac-

cumulative method by ionization chamber.

Page 17 of 199


In the same place we determined the radon exhalation from different depth re-

spectively 20 cm, 40 cm, 60 cm, 80 cm. We also determined the radon soil gas

concentration in these depths.

In the case of the accumulation method for the best fitting we need a measure-

ment as long as possible. If the measurement time is too long the main problems

are the back diffusion and the meteorological factors.

It is reasonable to use the longest measuring cycle because in this case the un-

certainties of radon activity concentration measurements are the smallest.

The radon activity concentration values did not fit perfectly with the theoretical

curve in case of soil concentration gradient method. Probably the reasons are the

inhomogeneous and perturbed soil structure. We suggest exposure time 3–4 days

depending on the depth of measurement points.

Page 18 of 199


A COMPARATIVE ANALYSIS OF THE HEAVYMETALS, HEAVY NATURAL RADIONUCLIDESCONCENTRATIONS AND BIOINDICATION AS-SAY OF WATER SAMPLED FROM A RADIUMPRODUCTION INDUSTRY STORAGE CELL

TERRITORY

T. Evseeva1), S. Geras’kin2), Shuktomova I.1), A. Taskaev1)

1) Institute of Biology of Komi Scientific Center, Ural Division RAS, 167982 28,

Kommunisticheskaya st., Syktyvkar, Russia


2) Russian Institute of Agricultural Radiology and Agroecology, 249020,

Obninsk, Kaluga Region, RUSSIA

Mining and processing industries are main sources of environmental pollutants:

heavy metals, heavy natural radionuclides and others. This leads to many ecosys-

tem undergoing a simultaneous potential stress from chemical and radioactive tox-

icants. Our previous works demonstrates that in order to achieve pollutant screen-

ing, it is not sufficient to determine the pollutants concentration only. The chemical

analysis data reveals nothing about the total exposure an organism has received.

In contrast to the specific nature of assessments on exposure, effect studies inte-Page 19 of 199


grate the impacts of all mutagenic activities, including synergistic and antagonistic

effects. Consequently, adequate conclusions on the risk due to environment con-

tamination need to be based on the additional simultaneous use of toxicity and ge-

netic toxicity tests.

In this report results of the simultaneous use of bioindication and chemical analy-

sis approaches for estimation of the chemical and radioactive contamination of the

water from reservoirs located near the radium production industry storage cell are

represented for the first time. The storage cell is situated in the settlement of Vod-

niy (Komi Republic, Russia). A plant for the production of radium from underwater

had been in operation at this place from 1931 until 1956. In particular, in this re-

port will represent results of:

comparative analysis of modern and observed in 1959–1960 levels of radioactive

and chemical contamination of the water from reservoirs located near the radium

production industry storage cell;

genetic toxicity and toxicity assay of water sampled from a radium production in-

dustry storage cell territory by means of Allium-test.

Further to this, the attempts were made to understand whether or not any correla-

tion existed between heavy metals, heavy natural radionuclides concentrations

and observed biological effects. In addition, possible mechanisms of genotoxic

and toxic action of radioactive and chemical combined environmental contamina-

tion will discuss.

Page 20 of 199


A COMPARATIVE ANALYSIS OFBIOLOGICAL EFFECTS IN PLANTS

INHABITING TWO RUSSIAN REGIONS WITHA HIGHER LEVEL OF HEAVY NATURAL

RADIONUCLIDES

S. Geras’kin1), T. Evseeva2), A. Taskaev 2), I. Shuktomova2)

1) Russian Institute of Agricultural Radiology and Agroecology, 249020,

Obninsk, Kaluga Region, RUSSIA


2) Institute of Biology of Komi Scientific Center, Ural Division RAS, 167982 28,

Kommunisticheskaya st., Syktyvkar, RUSSIA

Extracted on a ground surface rocks and reservoir water are contain heavy natural

radionuclides (HNR), which both -, -, -emitters and high-toxic chemical ele-

ments. As it is the case for man, the HNR seem to constitute a preponderant

source of exposure to natural radiation for the majority of living wild organisms.

Despite of rather high HNR levels in

a refuse heaps, the problem on their possible effects on plants and animals inhab-

iting spoil heaps of mines was investigated only in a few studies.

Page 21 of 199


In this report the data on a content of isotopes of U, Ra and Th in soils and plants

of two northern region of Russia (Komi Republic (radium-gearing waste) and

South Yakutia (uranium-containing waste pile)) are represented. Despite of similar

character of a radioactive contamination and a close climatic conditions, the radio-

biological effects in plants from these regions were drastically differing. The higher

frequency of aberrant cells in Vicia cracca L. germs from Komi Republic site was

found. Moreover, the elimination of bearing chlorophyll mutations plants was ob-

served in these Vicia cracca L. populations. The seeds of Vicia cracca L. plants

from Komi Republic site were significantly more sensitively to acute -radiation

when compared with untreated control. In contrast, no significant difference in

aberrant cells frequency of alder trees seedlings growing on the South Yakutia site

was noted. In addition, the seeds from the alder trees populations growing in the

South Yakutia site appeared to be significantly more resistant to the acute radia-

tion exposure than the reference seeds.

The reason for these differences is not clear now. It is reasonable to assume that

at least some of this variability can be accounted for by differences in radiation ex-

posure structure. In Komi Republic site the contribution of the internal irradiation to

an equivalent dose in 3–3.5 times above share of the external -irradiation. Unlike

Komi Republic site, for South Yakutia site the external -irradiation (71–86%) play

a decisive role. Future studies will provide

Page 22 of 199


EXPOSURE FROM AN IGNEOUS PHOSPHATEMINE OPERATION

A.J. vd Westhuizen, Foskor

Republic of Soth Africa

The International Atomic Energy Agency Safety Series 115 and European Union

Council Directive 96/29/EURATOM have changed the profile of radiation protec-

tion completely, increasing the regulatory awareness of natural radiation and the

industries involved. Three major industries have been identified in terms of their

scope and the materials handled as industries requiring further attention. They are

the Oil & Gas Industry, the Zircon Industry and the Phosphate & Fertilizer Industry.

The Phosphate and associated Fertilizer industry has an added complication, be-

cause it has two distinct sources of raw material, e.g. being of igneous or sedi-

mentary origin. The sedimentary material has a dominant 238U series, with activi-

ties ranging from 1 Bq/g per isotope to as high as 5.7 Bq/g per isotope, but with

negligible 232Th content. The igneous material of the Phalaborwa Complex have

fairly low levels of 238U and its associated daughters, (less than 0.15 Bq/g per iso-

tope), but with elevated levels of 232Th when compared with the sedimentary mate-

rial. This paper will focus on the mining operations of an igneous source located in

South Africa.

The mine involved received a nuclear authorisation in 1993 under the auspices of

the Nuclear Energy Act, No 131 of 1993 and in the following years completed both

occupational and public risk assessments as required by the authorisation. This

paper place emphasis on the public risk assessment completed in 1999, the re-Page 23 of 199


sults of the subsequent routine monitoring program and expand on some of the

practical problems the company had to deal with.

The public risk assessment was conducted in an integrated manner, assessing

doses to members of the public via the atmospheric, aquatic and secondary path-

ways by the Nuclear Energy Corporation of South Africa and the subsequent rou-

tine monitoring program results evaluated and reported to the regulator by the

company itself.

In conclusion it will give a brief description of the current monitoring program with

a mention of possible future projects.

Page 24 of 199


RADIOLOGICAL RISK ASSESSMENT OFPHOSPHOGYPSUM PLASTERBOARDS IN

HOMES

A.J. vd Westhuizen, G.P. de Beer, Foskor

Republic of South Africa

Naturally occurring radioactive materials, or NORM, became the focus of regulato-

ry interest with the publication of International Atomic Energy Agency SS115 and

the subsequent publishing of European Council Directive 96/29/EURATOM. As a

result, strong focus was placed on the Phosphate and Fertiliser Industry not only

in Europe, but also South Africa. Foskor, together with the Fertiliser Society of

South Africa (FSSA) embarked on a national industry assessment program to

identify areas of risk as to ensure an optimised and cost-effective management

program.

Phosphogypsum is generated during the production process of phosphoric acid

from phosphate rock. Simplified reaction equations are as follow:

Ca3(PO4)2 + 3H2SO4 2H3PO4 + 3CaSO4

Ca3(PO4)2 + 4H3PO4 3Ca(H2PO4)2

3Ca(H2PO4)2 + 3H2SO4 3CaSO4 + 6H3PO4

The source material contains isotopes from the natural uranium and thorium de-

cay chains that may or may not follow the gypsum in the process. It is reported

Page 25 of 199


that approximately 80% of the Radium-226 follow the gypsum, whereas 86% of

the uranium and 70% of the thorium are found in the phosphoric acid. It is com-

mon practice to use phosphogypsum in the building process, such as in the manu-

facture of plasterboards for houses etc. (Ceilings are typically made from plaster-

board).

The following assessment utilises actual measurements and radon calculations to

asses a first order exposure risk for members of the public, when residing in a

dwelling with phosphogypsum plasterboard as part of the structure as well as to

the responsible builder in terms of occupational exposure. The assessment identi-

fy areas that may require further or more detailed investigation, depending on the

level of detail required by the regulatory authority and compare it with a similar

study conducted in Australia on sedimentary material.

Page 26 of 199


RAIL TRANSPORT OF IGNEOUS PHOSPHATEROCK

A.J. vd Westhuizen, G.P. de Beer

Republic of South Africa

The third Research Co-ordination Meeting on the Development of a Radiological

Basis for the Transport Safety Requirements for Low Specific Activity Materials

and Surface Contaminated Objects (LSA/SCO) was held in Cape Town, South

Africa on the 19th to 23rd of February 2001. It has been attended by the Chief Sci-

entific Investigators (CSI) from Brazil, Canada, France, Germany, South Africa

and the United Kingdom, with the IAEA acting as Scientific Secretary. In addition

to the CSI’s, Observers of South Africa and Japan participated.

A Phosphate Rock and Fertiliser Producer (South Africa) participated under ob-

server status during the event and agreed to repeat the zircon sand study for ig-

neous phosphate rock and -phosphoric acid to support the theoretical models al-

though the material is strictly speaking not subject to the requirements of “ST1:

Regulations for the safe transport of radioactive materials”.

This paper represents a partial fulfilment of the commitment, reporting on (a) the

occupational exposure of loading of the phosphate rock on the rail cars, transport

and unloading in the harbour (b) public exposure during rail transport and interim

storage in silos and (c) give some reference to undesired events, such as spillage.

This risk assessment is based on actual measurements where possible and will

only refer to modelling or theoretical calculations where no results are available.

Page 27 of 199


NORM IN BUILDING MATERIALS

Aliyev Chingiz

H. Cavid av., 29a, Baku, AZ 1143 AZERBAIJAN

Geology Institute of Azerbaijan National Academy of Sciences


Specific activity (Cef) of building materials depends on amount of radionuclides in

their composition. According to standards of radiation safety Cef should not exceed

a dose Bq/kg (Cef = CRa + 1.31CTh + 0.085CK). Gamma-spectrometric investiga-

tions in Azerbaijan demonstrated that Cef for building materials manufactured from

natural raw materials varied from 30 to 190 Bq/kg. Average Cef for Azerbaijan is 69

Bq/kg.

Products made from artificial materials should not contain radionuclides. Investi-

gations demonstrated that sometimes Cef 10 times exceeds standards and is 3800

Bq/kg at account of increased amount of radium. This strengthens hazard of their

utilization. Cases are known when sources of ionizing radiation have been lost

while manufacturing building blocks of cement and concrete. Being installed in

dwellings they create hazardous situation. Utilization of high-radioactive industrial

wastes to manufacture bricks or cement to lay floors was found out.

These data demonstrate urgency of constant control for quality of the products

used in construction of buildings and dwellings.

Page 28 of 199


The most effective and economic way of quality control of the building materials is

gamma-spectrometric analysis. This method is scientifically grounded and passed

though great practical expertise.

Page 29 of 199


NORM IN COAL

T.A. Zolotovitskaya

H. Cavid av., 29a, Baku, AZ 1143 AZERBAIJAN, Geology Institute of Azerbaijan

National Academy of Sciences


While combusting coal outburst occurs into the atmosphere: a great amount of

aerosol particles containing natural radionuclides (uranium, radium, thorium and

products of their decay). Concentration of radionuclides in different coals varies in

Bq/kg from 3 to 520 Bq/kg for 238U and from 3 to 320 Bq/kg for 232Th. Degree of ra-

dionuclide contamination of the environment depends on the original matter. For

this reason it is necessary to study radioactivity of coals and to select that which

contains the lowest amount of harmful matters. Concentration of radionuclides in

cinder grows 3–4 times as compared with the original matter as while combusting

coal the organic component burns out and concentration of radionuclides in cinder

and slog becomes higher.

Thus, during a slight growth of amount of uranium in coal – 90.7 Bq/kg and in ash

it might be 270.3 Bq/kg. Normally amount of uranium in ash varies 500–600 Bq/kg

but sometimes it is 1742 Bq/kg and even 3055 Bq/kg. This results in a heavy con-

tamination of the environment and causes problems with the removal of such ash.

Page 30 of 199


Knowing amount of radionuclides in coal and in ash, one can calculate safety level

of the environmental contamination and to increase efficiency of purifying to sub-

stitute radioactive coal by coal with lower amount of uranium.

Page 31 of 199


RADIONUCLIDE CONTAMINATION OF THENATURAL ENVIRONMENT OF ABSHERON

PENINSULA (AZERBAIJAN)

Sabina Aliyeva




The territory of Azerbaijan due to its geographical situation, the total combination

of nature-climate zones and the presentation of industrial potential is the unique

object of ecological researches.

One of the most ecologically problematic regions of Azerbaijan is Absheron Penin-

sula. The main factors of pollution in development of oil deposits are the oil and oil

products. Normal radioactive background in the Absheron peninsula varies from 4

to 10 μR/h.

The problem of pollution of oil-producing areas by the radionuclides of the natural

origin arises recently. Polluted by radionuclides surfaces and oil industrial equip-

ment are discovered at almost all exploration fields surrounding the large industrial

centre – Baku city. There were determined anomalous areas where intensity of

gamma-radiation reaches 600 μR/h. Besides, within the Absheron peninsula there

are iodine plants, the territory of which are also polluted by radionuclides of the

natural origin.

Page 32 of 199


The identification of the radionuclides showed that they were presented by the

group of uranium-radium, the content of which reaches the high concentrations.

One of the methods of reducing the ecological intensity on the oil fields can be the

utilization of underground salt brines and, probably, their usage for the medical

goals.

During the process of oil-gas fields exploration (especially in the offshore area of

the Caspian Sea) it is necessary to take environmental protection measures be-

fore geologic-exploration works linked with the study of radiation background of

the coastal-shelf zones and radioactivity of bottom sediments. At present there is

a large experience of radioecological works that can be used in creation of radia-

tion monitoring in Azerbaijan.

Page 33 of 199


MITIGATION METHODS IN SELECTIONPLACES OF CONSTRUCTION SITES

Aliyev Chingiz, Tamara Zolotovitskaya, Sabina Aliyeva




One of the main tasks in selection of construction sites is study of geologic struc-

ture. Tectonic faults within construction sites represent additional hazard for build-

ings. Radiometric methods allow to determine activity of fault dislocations. In ra-

dioactive fields of the earth crust only active tectonic dislocations and geodynamic

zones manifest themselves.

While planning construction works it is necessary to locate buildings outside the

hazardous areas. Results of surveys allowed to identify areas with increased

radon exhalation. It mitigates risk of hazardous radiation of people. According to

level of gamma-radiation areas of grounds of different lithologic composition are

identified.

In developed countries (USA, Canada) radon investigations were conducted to

evaluate high, middle and low level of radon exhalation. In these countries it is

used to choose less hazardous zones. In Russia radon survey for engineer-techni-

cal construction in different areas has been conducted more and more intensive

recently. This is also used for the studies of interrelation of distribution of ground

radon and amount of radon in buildings.Page 34 of 199


These problems have been discussed in China recently with account of mitigation

of radiation risk for population. This problem should be discussed in newly estab-

lished Radon Centre (Poland).

Page 35 of 199


NATURAL RADIONUCLIDES IN RARE EARTHINDUSTRY AND THEIR ENVIRONMENTAL

EFFECTS

Xiaolin Hou1), Weiyue Feng2)

1) Risø National Laboratory, NUK-202, DK-4000 Roskilde, DENMARK2) Institute of High Energy Physics, Chinese Academy of Science, Beijing,

CHINA

The environmental problem of naturally occurring radioactive material (NORM) in

phosphate, petroleum and natural gas, and coal industries have been well known

and widely investigated. But a few investigations were done for the occurring, mi-

gration and radiation problem to workers of NORM in rare earth industry. Uranium

and thorium are associated with rare earth ore. As high as 7% and 0.25% of Th

and U in rare earth ore was reported, all radionuclides in the uranium and thorium

decay series are therefore exist in the rare earth ore, and distribute in the working

place and waste in the rare earth industry. China has more than 70% of inventory

of rare earth ore, and produced 60.000 tons of rare earth products every year,

tens times of waste containing NORMs was therefore produced. It induced a rela-

tive environmental problem. The current status of NORM studies in rare earth in-

dustry in China is reviewed in this paper. The type and distribution of rare earth

ore in China and their radiation level is first introduced. The radiation level of work-

ing place in some rare earth factories is also presented, finally the concentrations

Page 36 of 199


of U, Th and their long-lived daughter radionuclides in the waste and their environ-

mental effects are reviewed.

Page 37 of 199


CRYING WOLF! HOW TO DEAL WITHPRESUMED RADIOACTIVE CONTAMINATION

Heldio P. Villar, Carlos de Austerlitz Campos

Centro Regional de Ciências Nucleares, Rua Cônego Barata, 999 – Tamarineira,

Recife, BRAZIL, 52110-120


Reports concerning the occurrence of malignancies and cancer cases among the

population caused by the presence of radioactive materials in the environment are

not unusual in Brazil. The country’s Nuclear Energy Commission, CNEN, is always

assigned to launch an investigation in such cases. As a result, human and finan-

cial resources are usually committed in operations that, more often than not, end

up by discovering that claims are not related to radiation. This time, alarmist re-

ports from the small town of Lajes Pintadas, in the backlands of the Brazilian

north-eastern state of Rio Grande do Norte, concerning the occurrence of stillborn

and malformed children and of cancer cases among the adult population, reached

the state capital. A team from the Regional Nuclear Sciences Centre, CNEN’s in-

stitute for the north-east, was dispatched to Lajes Pintadas to look for the effective

presence of environmental radionuclides and to investigate the reported occur-

rence of malignancies caused by radiation. Due to the well-known dangers related

to launching an investigation on a subject so controversial and prone to misinter-

pretation by the media and the public, a novel approach, both in technical and

philosophical terms, was attempted and that proved to be crucial for the successPage 38 of 199


of the whole undertaking: two years on, no more reports on health problems in La-

jes Pintadas were published.

Page 39 of 199


ENVIRONMENTAL RADIOLOGICAL IMPACTBY A FERTILIZER COMPLEX IN THE EBRO RIVER (SPAIN)

E. Costa1), J.A. Sanchez-Cabeza1), J. Garcia1), P. Masqué1), J.O.Grimaltb2)

1) Institut de Ciencies i Tecnologia Ambiental-Departament de Física,

Universitat Autónoma de Barcelona, 08193 Bellaterra, Barcelona, SPAIN2) Department of Environmental Chemistry, Institute of Chemical and

Environmental Research (CSIC), Jordi Girona 18, 08034-, Barcelona, SPAIN

In this work we report the distribution of U and Th series radionuclides in the dis-

posal area located in the vicinity of a fertilizer production complex in the Ebro river.

This industry produces dicalcium phosphate (DCP), used as a source of calcium

and phosphorus for domestic animals. The wastes are released into 5 dumping

areas in the Flix hydro electrical reservoir, producing the presence of 5 sedimenta-

ry lobules near the river shore. A sediment core (longitude circa 1.5 m) was col-

lected from each lobule. The concentrations of natural radionuclides determined

by -spectrometry, clearly showed the enhancement of concentrations in the sedi-

ments since the beginning of production in 1973. The activities observed ranged

from 238U (42–11 000 Bq kg-1), 210Pb (32–5600 Bq kg-1), 226Ra (21–9900 Bq kg-1),232Th (10–163 Bq kg-1). These concentrations may be of concern as it is well

known that radionuclides such as 210Pb can be accumulated by certain aquatic or-

Page 40 of 199


ganisms. However, concentrations in water samples collected downstream, until

the Ebro delta, have not shown the presence of enhanced levels of 226Ra.

Page 41 of 199


ASSESSMENT OF NORM IN SAUDI ARAMCOFACILITIES

Khalid Mously, Osama Fageeha, Michael Cowie

Environmental Protection Department, Saudi Aramco

Dhahran 31311, SAUDI ARABIA


It has been established that Naturally Occurring Radioactive Materials (NORM)

accumulates at various locations along the oil/gas production process. Compo-

nents such as wellheads, separation vessels, pumps, and other processing equip-

ment can become NORM contaminated. This can create a potential radiation haz-

ard to workers and the environment.

Saudi Aramco Environmental Protection Department initiated a program to identify

the extent, form and level of NORM contamination associated with their opera-

tions. This paper provides an overview of Saudi Aramco’s NORM assessment pro-

gram and highlights lessons learned and knowledge gained.

Page 42 of 199


THE 238U–234TH EQUILIBRIUM IN SOILSAMPLES

D. Mrđa, I. Bikit, J. Slivka, M. Vesković, Lj. Čonkić, N. Todorović,E. Varga, S. Ćurčić

Department of Physics, Faculty of Sciences, University of Novi Sad, Trg Dositeja

Obradovica 4, 21 000 Novi Sad, SERBIA AND MONTENEGRO


At gamma-spectrometric measurements on environmental samples the 238U activi-

ty is determined from the gamma-lines of its first daughters 234Th and 234Pa. The

24.1 d half-life of 234Th might be in principle sufficient to disturb the 238U–234Th equi-

librium in environmental samples. In few recent articles the possibility of quick 238U

determination by means of gamma-spectroscopy was challenged on this base. In

the paper we present the results of gamma-spectroscopic measurements on soil

samples performed immediately after sampling and about 1 year after the sam-

pling. The 238U–234Th equilibrium in fresh samples is discussed and the limits of the

accuracy of quick 238U determination are presented.

Page 43 of 199


RADIOACTIVITY OF THE FOOD AT NOVI SADMARKETS

Ester Z. Varga, Ištvan S. Bikit, Jaroslav M. Slivka, Nataša M. Žik-ić-Todorović,

Miroslav J. Vesković, Ljiljana U. Čonkić, Dušan S. Mrđa

1) Department of Physics, Faculty of Sciences,2) University of Novi Sad, SERBIA AND MONTENEGRO

3) Corresponding author: Ester Varga,4) Department of Physics, Faculty of Sciences, Trg Dositeja Obradovića 4,

21000 Novi Sad, SERBIA AND MONTENEGRO, tel/fax:+381 21 455318


Foods bought at Novi Sad markets were investigated by gamma-spectrometric

measurements. Milk and dairy products, cereals and cereals products, fruit, veg-

etable, meat and meat products, tea, herb, salt, mineral water, cacao etc. were

collected. The activity concentration of 20 radionuclides in each sample was mea-

sured for 50 000 s. The average radiation ingestion dose is estimated only for ra-

dionuclide 40K for all foodstuff groups and the results are compared with the re-

sults of earlier measurements.

Page 44 of 199


NATURAL RESTORATION OF A SPANISHESTUARY HISTORICALLY AFFECTED BYANTHROPOGENIC INPUTS OF NATURAL

RADIONUCLIDES

M. Villa1), A. Absi2), H. P. Moreno3), R. García-Tenorio2), G. Manjón2)

1) Facultad de Física. Universidad de Sevilla. Departamento de Física

Atómica, Molecular y Nuclear. Av. Reina Mercedes, s/n. 41008-Sevilla, SPAIN2) E. T. S. Arquitectura. Universidad de Sevilla, SPAIN. Departamento de

Física Aplicada II. Av. Reina Mercedes, 2. 41012-Sevilla


3) E. U. Arquitectura Técnica. Universidad de Sevilla. Departamento de Física

Aplicada II. Av. Reina Mercedes, 2. 41012-Sevilla, SPAIN

The Odiel estuary, placed in the southwest of Spain, has been historically affected

by the waste releases of several factories devoted to the production of phosphoric

acid and phosphate fertilizers. A portion of the wastes was directly released into

the Odiel River and other portion, about 80%, were stored in air opened piles,

which could be affected by tidal processes. It is well known that these wastes are

clearly enriched in radionuclides belonging to the uranium-series; being quite well

documented the clear radioactive impact produced by them in several compart-

ments of this estuary.

Page 45 of 199


But the waste policy of the commented factories drastically changed in 1998.

Since this year all the wastes are stored in well-protected piles without interaction

with the surrounding environment. For instance, the water used for transferring

these wastes is recycled. The consequences of the new wastes treatment rela-

tives to the radioactive evolution of the estuarine environment are the main objec-

tive of this work. For that, we have studied the time evolution of activity concentra-

tion of several natural radionuclides in the estuary.

According to the previous studies, which have described the radioactive impact

before 1998, the natural radionuclides more relevant are 226Ra, 238U, 234U and210Po. In order to analyse, since the interruption of the releases until today, the

time evolution of the activity concentrations of such radionuclides in the estuary,

water and sediment samples were collected in three different campaigns (1999,

2001 and 2002). These results as well as their activity ratios are shown in this

work and compared to the observed ones before 1998, when the releases oc-

curred, showing that the contamination by natural radionuclides of the estuary is

clearly decreasing nowadays. According to this tendency, the activity concentra-

tion enhancements caused by phosphoric factories, and consequently their ra-

dioactive impact, can be neglected in few years.

Page 46 of 199


TENORM REGULATORY FRAMEWORK INBRAZIL

Horst Fernandes, Mariza Franklin, Monica Pires do Rio

Instituto de Radioproteção e Dosimetria (IRD), BRAZIL

Comissão Nacional de Energia Nuclear (CNEN), BRAZIL

Mining activities in Brazil are spread all over the territory. Many of these industries

are suspected to cause undue exposures of workers and members of the public.

Because of that, the Brazilian Nuclear Energy Commission (CNEN) through the

Institute of Radiation Protection and Dosimetry (IRD) carried out a comprehensive

investigation work to detect the most important ones, in respect to potential radio-

logical impacts, and formulate the basis of a national regulatory framework to deal

with the problem.

The work selected some ore processing industries, e.g., coal, niobium, phosphate

and gold mining industries to be investigated. In parallel, the situation of the gas

and oil industries, as well as from other industries like mineral sands and tin pro-

cessing plants have been investigated by means of non-regulatory inspections.

Work methodology consisted of the examination of the individual operational pro-

cess. Residues and liquid effluents were sampled from every single release point.

The working places were also characterized by means of dust sampling, radon

and gamma radiation measurements. The mobility of radionuclides from the

wastes was assessed as well as the overall exposure of members of the general

public, both in present (operational) and future (post-operational) scenarios.

Page 47 of 199


The collected data permitted the construction of a robust data-base indicating the

occurrence of major areas to be addressed in terms of remediation/clean up activ-

ities.

The results allowed the regulatory authority to issue a Regulatory Standard with

the Brazilian Department of Mineral Production (DNPM) – CNEN.NE.4.10 (www.c-

nen.br). The standard divides the installations in three categories according to the

total activity concentrations in the ore (or any residue) and the radiological dose.

The first category encompasses industries that show activity concentrations above

500 Bq.g-1 and doses above 1.0 mSv.y-1; the second encompasses installations

that lies down in the range between 500–10 Bq.g-1, and the third one involves in-

dustries where the concentrations are smaller than 10 Bq.g-1 and doses bellow 1.0

mSv-1. Different requirements are made to industries lying down in these ranges.

As a result, it is expected that many of them will have to adopt remediation/clean

up strategies that will require the assistance of specialized technical work.

Page 48 of 199


THE FIRST RADON MAP OF VOJVODINA

S. Ćurčić, I. Bikit, Lj. Čonkić, M. Vesković, J. Slivka, Lj. Čonkić, E.Varga, N. Žikić-Todorović, D. Mrđa

Department of Physics, Faculty of Sciences, University of Novi Sad, Novi Sad,

SERBIA AND MONTENEGRO, Trg Dositeja Obradovica 4, 21 000 Novi Sad


Radon is a naturally occurring radioactive gas. Radon is the alpha emitter and de-

cays to short-lived daughters (218Po, 214Pb, 214Bi and 214Po). Radon partially decays

in material where it has been generated and partially moves rapidly by concentra-

tion-driven diffusion into the open air. Underlying soil is the main source of indoor

radon. However, building’s materials also may contribute to elevated indoor radon

concentration, especially in combination with low ventilation. In this paper the re-

sults of the first radon mapping in Vojvodina are presented. Indoor radon activity

concentration in air has been measured at the whole area of the province Vojvodi-

na (on about 2000 locations) by plastic track detectors CR-39. On the base of the

obtained results, the average indoor activity concentrations of 222Rn for individual

municipalities and for the whole province of Vojvodina (144 ± 120) Bq/m3 were es-

timated.

Almost 20% of the measurements are over the 200 Bq/m3 and 4% of the mea-

surements are significantly elevated indoor radon concentrations. The results are

above the expected values for the plains districts, despite the normal concentra-

Page 49 of 199


tions of 238U, maybe due to underground waters. The dependence of indoor radon

on the location and type of the houses and flats is discussed.

Page 50 of 199


EVALUATION OF OCCUPATIONALRADIOLOGICAL EXPOSURES ASSOCIATED

WITH FLY ASHES FROM FRENCH COALPOWER PLANTS

Jean-Pierre Degrange, Samuel Lepicard

CEPN, BP-48, 92263, Fontenay-aux-Roses, FRANCE


The French Ministry of Health is preparing a series of decrees for transposing into

French regulation the Euratom 96/29 Directive title VII concerning in particular the

work activities where natural radioactive substances are handled and used, but

not for their radioactive, fertile or fissile properties. Coal power stations belong to a

preliminary list of industrial sectors potentially concerned by this transposition and

the decrees' calendar of preparation includes a consultation period allowing to col-

lect information about the possible dosimetric impacts on various population

groups of these industrial sectors. At the request of the two French operators of

coal power stations, Electricité de France (EDF) and the National Company of

Electricity and Thermics (SNET), CEPN has evaluated occupational radiological

exposures resulting from the industrial activities which bring into play fly ashes

produced by the French coal power stations.

Page 51 of 199


In a first step, the various stages of the French fly ashes cycle were studied,

namely their production, handling and transport, storage, and recycling (mainly in

building materials and road constructions). In a second step, reference groups of

workers likely to receive significant doses were identified. Finally, a series of expo-

sure scenarios, aiming to be both conservative and realistic, were described on

the basis of realistic exposure data (when available) together with generic values

and simplifying assumptions. In the absence of dosimetric measurements, individ-

ual exposures were evaluated using appropriate models for external irradiation,

dust and radon inhalation, ingestion and transfer in the biosphere.

Estimated annual individual doses range from fractions to hundreds of microsiev-

erts per year and maximum doses are associated with situations where external

contribution is largely dominating (tailings works, road construction). Sensitivity

analyses were performed to evaluate the impact on dose estimates of possible

variations of the calculation parameters. This study should provide both industrial

and regulatory bodies with a methodological approach enabling to pinpoint situa-

tions in the French context that may be calling for a particular attention

in terms of radiation protection.

This paper summarises the methodology of the assessment as well as the charac-

teristics and individual doses results associated with the most important scenarios.

Page 52 of 199


RECYCLING OF 232TH CONTAMINATEDTUNGSTEN SCRAP

U. Quade, W. Müller

Siempelkamp Nukleartechnik GmbH Siempelkampstrasse 45 D 47803 Krefeld

GERMANY


In Krefeld, Germany, Siempelkamp operates a melting plant to treat steel scrap

contaminated with natural radioactivity, mercury and other chemical and toxical

substances. The so-called GERTA plant is licensed according to the German BIm-

SchG (federal law on protection against environmental pollution).

The facility is equipped with a net frequency induction furnace and has an annual

capacity of 2000 t/a. The purpose is to produce a final metal product, which is

completely free of all contamination and can be released to the steel cycle without

any limitations.

So far, the input has been carbon or stainless steels with contamination of 226Ra

as main nuclide in case of NORM contamination or elementary mercury from oil

and gas producing facilities or from chlorine electrolysis.

In a recent project, more than 130 t of tungsten and molybdenum contaminated

with radioactive 232Th from the production of welding electrodes, have been suc-

cessfully decontaminated and have been converted into a Fe-W-Mo-alloy, which

could be sold as a high value product. By this way, up to 25 wt-% of

Page 53 of 199


tungsten/molybdenum could be dissolved in an iron melt and the thorium-oxide

could be transferred to the slag.

The slag can be released for recycling, if the 1 mSv/a-criterium for workers and

population according to the current German radiation protection ordinance is full-

filled.

In an expert opinion it was ascertained, that according to the typical distribution of

throughput in the GERTA plant, specific activities up to 65 Bq/g 232Th and 87 Bq/g226Ra can be accepted in the slag.

This paper describes the “tungsten project” in terms of metallurgy, radiation pro-

tection and legislation.

Page 54 of 199


ON THE MEASUREMENT OF 40K IN NATURALAND SYNTHETIC MATERIALS BY THE

METHOD OF HIGH-RESOLUTION GAMMA-RAY SPECTROMETRY

N. Lavi1), F. Groppi2), Z.B. Alfassi3)

1) Environmental Services Company Ltd., Environmental Radiation Laboratory,

Tel Aviv, ISRAEL


2) Università degli Studi and INFN-Milano, L.A.S.A., via Filli Cervi201, I-20090

Segrate, Milano, ITALY

e-mail: @mi.infn.it

3) Department of Nuclear Engineering, Ben Gurion University, Beer Sheva,

ISRAEL


In the measurement of Natural Occuring Radioactive Material (NORM) the con-

centrations of 40K, 232Th and 238U are measured by passive gamma ray spectrome-

try with either HPGe or NaI(Tl) detectors.

Page 55 of 199


40K is measured through its 1460.8 line. However till now it was ignored that this

line is mixed with the 1459.2 keV line of 228Ac from the the chain of 232Th. A correc-

tion must be made for this contribution.

All the data in literature has wrong data about the concentration of 40K although in

many cases the error is less than 1%. However there are cases of considerably

higher errors. It should be emphasized that even if the correction in 40K concentra-

tion is large the correction of external dose index is negligible due to the higher

weighing factor for 232Th than for 40K (by at least a factor of 10).

Page 56 of 199


SOIL CONTAMINATION IN A RURAL SITEUSED FOR RARE EARTH INDUSTRY

BY-PRODUCT DISPOSAL

C. Briquet1), D. Lauria2)

1) Comissão Nacional de Energia Nuclear/CNEN Rua General Severiano, 90

Rio de Janeiro, BRAZIL


2) Instituto de Radioproteção e Dosimetria/CNEN Av. Salvador Allende, s/no

Rio de Janeiro, BRAZIL


In the past the processing of monazite aiming production of rare earth elements

was performed in São Paulo state. This industry produced large quantities of

byproducts and wastes: cake II (uranium and thorium hydroxides) and mesothori-

um cake (Ba(Ra)SO4). At that time the National Commission of Nuclear Energy –

CNEN didn’t have regulations for this kind of activities. At the moment CNEN is

preparing regulations regarding NORM processing industries and also for inter-

vention situations.

Between 1975 and 1981, 3500 tons of cake II was stored in seven rectangular

concrete pits three meters deep, surrounded by 30 cm concrete walls and floor,

which were built for this purpose in a country area of São Paulo state, a region of

farms. A river flows across the property into the public water supply of a city, 12

Page 57 of 199


km far from the site. Activity concentrations of 228Ra varying from 0.5 to 50 Bq/g

were identified in the soil by a preliminary survey, which indicates that the site was

contaminated by radionuclides of the 232Th series from the by-products and

wastes. The inhabitants of the region are very concerned about the situation.

The purpose of this paper is to identify and characterize the extension of the con-

tamination in the soil and to derive guideline concentrations with the goal of the

site remediation. Besides, an assessment of public risk perception has been per-

formed. This assessment will give support to introduce the public participation in

remediation process and establish a work methodology, in order to obtain a more

effective communication between regulator and society.

Page 58 of 199


PASSIVE ANTINEUTRINO SOUNDING OFSPATIAL DISTRIBUTION OF RADIOACTIVE

ELEMENTS IN THE EARTH DEPTHS

V.D. Rusov1), V.M. Pavlovich2), V.M. Vaschenko3)

1) Odessa National Polytechnic University, UKRAINE2) Kiev Institute for Nuclear Research, UKRAINE

3) Ukrainian Antarctic Center, UKRAINE

The method is offered of the Earth depth antineutrino sounding with the help of

antineutrino registration by several detectors located at different points of the

Earth surface.

The modern knowledge about structure, element composition, physical condition

of plutonic layers of the earth crust, the mantle and core of the Earth are insuffi-

cient for the solution of many problems. For example, the information about the el-

ement structure of the Earth mantle and core can help during refinement of an

earth type planet formation models its evolution. At the same time, the knowledge

of quantity and spatial distribution of radioactive elements in the Earth depth will

enable to update a heat balance of the Earth, that can essentially influence on the

development of climate models and methods of forecasting of climate change,

and also, in general, on our ideas about a nature of energy-mass processes in

plutonic entrails of the Earth. The especially practical problem of obtaining of more

detail contours of radioactive elements fields is also important. All these problems

are connected with determination of spatial distribution and quantity of radioactive

Page 59 of 199


elements in the Earth depth, and its can be solved with the help of antineutrino

sounding of our planet.

Except the type and quantity of nucleous, which emit antineutrino, the determina-

tion of a spatial distribution of these nucleous is very important. It can be made

with the help of a passive detection and ranging methods, which have reached

high perfection during the last years due to practical requirements of medicine,

military applications and development of computer equipment. The problem of an-

tineutrino sounding of the Earth depth is similar with some differences to problems

of a medical tomography and problem of a passive electromagnetic or sound de-

tection and ranging of moving objects.

The technology of passive sounding requires large interdetection base. The size

of this base should be as greatest as possible in order to achive the maximum ac-

curacy of measurements. Therefore for sounding of the planet depth, it is neces-

sary to place detectors at the opposite points of the globe, for example, one detec-

tor is placed in Antarctic Continent, second – in Europe, third – in Asia and so on.

All detectors should be connected by the common electronic circuit, which will en-

sure correlation measurements.

The arrangement of one or several detectors in Antarctic Continent or Greenland

can be useful from the several points of view. First, it can be placed under a thick

enough layer of ice, which will ensure the space radiation detector screening. Sec-

ondly, ice can serve as the detector material, and the size of the detector in this

case will limit only by available quantity of photomultipliers and detectors of neu-

trons, so the size of the detector will be determined by the accessible cost and ex-

perimental expediency.

Thus, the organization of antineutrino-correlation experiments with the purpose of

passive sounding of the Earth, on the one hand, opens the exclusive capabilities

of the direct identification of a radioactive element spatial distribution in the Earth

mantle and core, and on the other hand, can help to solve some relevant prob-

lems during the refinement of the planet formation models. For example, to find

out the connection between the field of magma speed and the complex rotation

and transmition motion of continental plates.

Page 60 of 199


STATUS OF RADON DOSIMETRY INZAMBIAN UNDERGROUND MINES

P. Hayumbu11), S. Mulenga2), M. Nomai1), P. Mulenga1), R. Katebe1),P. Shaba1), T. Chunga3), D. Inambao3), F. Mangala2), P. Tembo2), Y.

Malama2)

1) National Institute for Scientific and Industrial Research (NISIR), Lusaka,

ZAMBIA2) Konkola Copper Mines plc (KCM), Chingola, ZAMBIA3) Radiation Protection Service (RPS), Lusaka, ZAMBIA

The Zambian economy has significantly relied on copper and cobalt mining in the

relatively uraniferrous Katanga Basin with a potential hazard of radon for over 50

years now. The radon preliminary survey of Hayumbu et al (1998) showed that at

least 30% of the 42 randomly sampled sites in 8 underground mines had radon

levels over 1000 Bq/m3 (IAEA, 1996).

This paper outlines on-going radon dosimetry activities in Zambian underground

mines and presents radon grab sampling and personal measurements at one of

the mines identified to have high radon concentrations during the preliminary sur-

vey.

References

Hayumbu P., Malikana E.M. and Hussain M.M. (1998), Preliminary Survey of

Radon Levels in Some Copper/Cobalt/Pyrite Underground Mines in Zambia,

NISIR, Lusaka.

Page 61 of 199


International Atomic Energy Agency (IAEA), (1996), IAEA Basic Safety Series No.

115, Vienna.

0.005.00

10.0015.0020.0025.0030.0035.0040.00

S2 S3 S4 S5 S6 S7 S9 S10 S11 S14

Grab Sampling Site

Rad

on

Do

se (mS

v/y)

Figure 1. Radon Grab Sample Measurements of September 2002

0

1

2

3

4

5

6

7

M1 M2 M3 M4 M5 M6 M7 M8 M9 M10 M11 M12 M13 M14 M15 M16 M17 M18 M19 M20 M21 M22 M23 M24 M25 M26 M27 M28 M29 M30

Worker ID

Mea

sure

d D

ose

(mS

v/y)

Dose

Figure 2. Radon Personal Measurements of September 2002 – June 2003

Page 62 of 199


THE RADON DOSEMETER COMBININGCHARCOAL CANISTERS AND TLD

DETECTORS TYPE MCP-N (LIF: MG, CU, P)

Joanna Bogacz, Maciej Budzanowski, Ryszard Haber

The Henryk Niewodniczański Institute of Nuclear Physics Polish Academy of

Sciences,

PL-31-342 Kraków, Radzikowskiego 152 St., POLAND


A method of measurement of radon concentration in air is based on high-sensitivi-

ty LiF: Mg, Cu, P (MCP-N, TLD Poland) thermoluminescent detectors installed in

charcoal canisters [1].

To increase the radon measurement accuracy and to decrease detection thresh-

old the new charcoal canister construction has been proposed. This makes possi-

ble to measure low radon concentration typically occurring in dwellings.

A calibration curve has been determined by exposing the canisters for 72 h in the

calibration chamber IFJ-KR-600 with a radon concentration from 50 to 500 Bq/m3.

It has been found that in these conditions the signal registered by the TL detectors

is proportional to the 222Rn concentration and the lowest limit of detection is at a

level of 50 Bq/m3.

The proposed method can be used in a routine measurements radon concentra-

tion in dwellings.

Page 63 of 199


J. Bogacz, J. Mazur, J. Swakoń, M. Budzanowski, P. Olko MCP-N (LiF: Mg, Cu, P)

TLDs for radon measurements with charcoal canisters. Rad. Prot. Dos. 101(1-4),

267-270 (2002).

Page 64 of 199


NORM AND DECOMMISSIONING OFNUCLEAR FACILITIES

Kurt Robert Geber

Diplomate of the American Board of Health Physics, 8909 Colchester Ridge Road

Knoxville, Tennessee 37922, UNITED STATES


Recent experience in the United States has shown that NORM (naturally occurring

radioactive material) can cause interference in the final status survey which is nec-

essary to release a decommissioned nuclear facility from its license. Radiological

assessments conducted in support of license termination often do not discriminate

between nuclear materials which are part of the nuclear fuel cycle and those that

are naturally occurring in the environment. Because of the greater linear energy

transfer of alpha radiations, those naturally occurring isotopes that decay with the

emission of an alpha particle are the cause of particular consternation. In addition,

interpretation of data is confounded by the contributions of radiocaesium, iodine,

and technecium contaminations deposited in the environment from nuclear

weapons testing and accidents such as that which occurred at Chernobyl in 1986.

Discussed are experiences and effective methods for discriminating between

NORM and licensed materials during the application of field scanning and data re-

duction.

Page 65 of 199


IMPORTANCE OF SAMPLING IN RELATIONOF THE GAMMA SPECTROSCOPIC

ANALYSESOF NORM MATERIAL

L.P.M. van Velzen, C.W.M. Timmermans

NRG vof, THE NETHERLANDS

In the Netherlands problems arose with naturally occurring radioactive materials

(NORM) and enhanced concentrations of NORM (TENORM; Technical Enhanced

NORM) in the mid eighties of the last century and was due to discussions about

reuse of fly ash in building and road construction materials.

Gamma spectroscopic analyses of NORM and TENORM samples were at that

time still in its infancy. Nowadays different gamma spectroscopic analyse tech-

niques exists all with their specific accuracy.

Nowadays state of the art techniques are able to assess the specific activity of

uranium and thorium chains present in the variety of NORM and TENORM materi-

al with accuracies between 2 and 10%, even when daughters nuclides are not in

equilibrium with their mothers.

This means in practice that the error due to sampling of NORM material has be-

come and will be more and more important by the radiological characterization of

samples of NORM and TENORM materials. This importance will also increase by

implementing the EC directive L 159, 1996 in national legalisations of the Euro-

Page 66 of 199


pean Community member states. The specific activity of samples has then to be

calculated according to the weighted sum method as described in EC directive

L 159.

An overview of the different (existing) gamma spectroscopic analyse techniques,

from straight forward up to state of the art techniques, will be presented including

their unique advantages and disadvantages.

Further special attention will be given to representative sampling of NORM and

TENORM materials in practice, in order to minimize sampling error and thus mini-

mizing the overall error. Applicable standards and guidelines will be discussed and

also how to comply with these standards and guidelines in practice.

Page 67 of 199


FACTORS CONTROLING MEASUREMENTSOF MASS RADON EXHALATION

COEFFICIENT

Nguyen Dinh Chau, Stefan J. Kalita, Edward Chruściel, ŁukaszProkólski

Faculty of Physics and Nuclear Techniques, AGH University of Sciences and

Technology, Al. Mickiewicza 30, 30-059 Krakow, POLAND

The determination of mass radon exhalation coefficient usually consists of mea-

surements of radon contents in an emanation chamber containing a certain sam-

ple of investigated material as a function of radon growth time. The procedure

seems to be simple, however results of radon exhalation coefficient measurement

of the same investigated material from different laboratories usually differ. To an-

swer the question, the authors attempted to investigate some factors such: sam-

ple mass, the ratio of a sample to emanation chamber volumes (volume ratio

Vp/Vk), sample granulation and moisture.

To investigate the above mentioned factors an emanation chamber of a volume of

10 dm3 and a Lucas cell with radiometer pylon AB-5 were used. The measurement

procedure of the radon exhalation coefficient is described as follows: an investi-

gated sample of a known mass and volume was closed tightly in the emanation

chamber, then the growing of radon content in the chamber was measured. The

radon contents were measured every 24 hours or so. The typical curve describing

the relation between the radon content (N) in the emanation chamber and time (t)

Page 68 of 199


is presented in Fig. 1. The curve of Fig. 1 can be presented by a well known equa-

tion

N(t) = a(1 – exp(–bt))where a = (Em·b)/m, b is decay constants of radon, Em is the mass radon exhala-

tion coefficient [Bq·s-1·kg-1] and a – sample mass [kg]. In Tables 1, 2 and 3, the

measured values of radon exhalation coefficient are presented for samples of the

different mass, different volume ratios Vp/Vk, different grain sizes and humidity.

The results given in Tables 1a & 1b show that the measured values of radon ex-

halation coefficient strongly depend on physical sample parameters. So they

should be reported together with the measured values of mass radon exhalation

coefficient. The trial of explanation of this phenomenon will be published by Chau

et al (2004).

This work was partly sponsored by the Polish Radon Center

Chau N.D., Kalita K.J., Chruściel E., Prokólski Ł. 2004 „Factors controling mea-

surements of mass radon exhalation coefficient”, Journal of Environmental Ra-

dioactivity (under preparation).

Neznal M., 2002, The international measurement of mass radon exhallation coeffi-

cient of some bulding materials. Unpublished raport, Czech Republic, September

2002.

Table 1. Table 2. Table 3.

Mass [kg] Vp/VkEm 2

(Bq.s-1·kg-1)0.05 0.0057 185150.10 0.0140 189120.20 0.0273 20980.35 0.0412 21570.50 0.0570 21260.70 0.0800 17581.00 0.1130 1684

Grain sizesEm 2

(Bq.s-1·kg-1)

Humidity

[%]

Em 2

[Bq.s-1·kg-1]<1 mm 1656 0 12941–2 mm 1675 2 212 62–4 mm 1707 6 30211>4 mm 22511 10 2177– – – –– – – –– – – –

Page 69 of 199


0 50 100 150 200 250 3000

10

20

30

40

50

60

Rado

n co

ncen

tratio

n (Bq

)

Time (h)

Fig. 1. The typical curve describing a relation between Rn content & time

Page 70 of 199


CONCENTRATIONS OF 222RN INGROUNDWATERS FLOWING THROUGHDIFFERENT CRYSTALLINE ROCKS: AN

EXAMPLE FROM ŚLĘŻA MASSIF (POLAND)

Tadeusz A. Przylibski

Wrocław University of Technology, Faculty of Mining, Division of Geology and

Mineral Waters, Wybrzeże S. Wyspiańskiego 27, 50-370 Wrocław, POLAND

Ślęża Massif is situated in the south-western part of Poland, about 30 km SW of

Wrocław, the capital city of Lower Silesia. The geological setting of the research

area is typical of the Sudety Mountains. Different types of crystalline rocks, both of

igneous and metamorphic origin, occur on the area of 25 km2. On the surface of

this relatively small area, Lower Carboniferous to Lower Permian Strzegom Sobót-

ka Granite and Devonian Ślęża Ophiolite are uncovered. The result is the occur-

rence of granites, gabbros, amphibolites and serpentinites, directly neighbouring

on each other.

Page 71 of 199


The author selected this area for determining the influence of rock type on the

concentration of 222Rn dissolved in groundwaters flowing through crystalline rocks.

The first stage of the research consisted of determining typical values of 222Rn

concentration in groundwaters flowing through different types of rocks and de-

scribing the scale of seasonal changes in 222Rn concentration. In the next stage of

the research, an attempt to apply 222Rn as one of the isotopic hydrogeochemical

tracers of pathways flow of fissure groundwaters will be undertaken.

The results show that the highest values of 222Rn concentration (reaching 229

Bq/dm3) were observed in groundwaters flowing out of springs located within gran-

ite, whereas the lowest one (1.1 Bq/dm3) was noted in a spring located within ser-

pentinite. The average 222Rn concentrations obtained in groundwaters flowing out

of two springs within granite were 174 and 85 Bq/dm3, whereas the average val-

ues in two springs located within amphibolites reached 7.3 and 8.7 Bq/dm3. The

average 222Rn concentrations in the springs flowing out of gabbro and serpentinite

amounted to 7.4 Bq/dm3 and 1.2 Bq/dm3 respectively. 222Rn concentration in the

groundwater flowing out of the spring located within serpentinites was stable dur-

ing the whole year, likewise the discharge of the spring. 222Rn concentrations be-

tween 1.1±0.3 and 1.3±0.3 Bq/dm3 were measured. On the other hand, 222Rn con-

centrations in waters flowing out of springs located within granite were character-

ized by distinct seasonal changes. The highest values (101 and 229 Bq/dm3) were

noted in summer, when the discharges were low, whereas the lowest ones (70

and 127 Bq/dm3) were recorded in spring, when the discharges of both springs

were high. In the remaining springs, radon concentration changes were of low

scale and irregular character. The obtained results will be crosschecked with data

obtained from other areas with similar geological structure, where crystalline rocks

play the principal role.

Page 72 of 199


RADON CHAMBERS – TECHNICAL DESIGNAND SOME CALIBRATION PROBLEMS

Krzysztof Kozak, Jadwiga Mazur, Mirosław Janik, TadeuszZdziarski, Ryszard Haber

The Henryk Niewodniczański Institute of Nuclear Physics, Polish Academy of

Sciences, PL-31-342 Kraków, Radzikowskiego 152 St., POLAND,


In the Natural Radioactivity Laboratory (at the H. Niewodniczański Institute of Nu-

clear Physics, PAS in Kraków) the special stand was designed and made for the

calibration of radon detectors and for other research activities. The stand is

equipped with two calibration chambers: IFJ-KR-200 (volume of 200 dm3) and IFJ-

KR-600 (volume of 600 dm3), two certificated radon sources (226Ra activities: 21.6

and 52.3 kBq), a pump, a flow meter, a manometer and a control panel. The

range of possible radon concentrations is from 45 Bq/m3 to 244 kBq/m3. The com-

puter software has been elaborated for planning and controlling the calibration

procedure.

The active devices (AlphaGUARD by Genitron GmbH) are used for checking the

obtained radon concentration inside the chamber. Two operation modes (diffusion

or flow-through) were applied and compared. The results of testing the long-term

tightness of the chambers are shown. The measurements of background radon

concentration have been made and the methods of decreasing this level are also

presented. The changeability of radon equilibrium factor F, as a function of radonPage 73 of 199


concentration and air humidity inside a chamber has been investigated and com-

pared with the respective measurements performed in larger chambers situated in

other laboratories in Poland.

Page 74 of 199


CALIBRATION OF SOIL PROBE FOR IN SITUPERMEABILITY MEASUREMENT

Mirosław Janik, Krzysztof Kozak


Sciences, PL-31-342 Kraków, Radzikowskiego 152 St., POLAND


Soil permeability is one of the important physical soil parameters for modeling

radon transport from soil to indoor. Permeability relates flow (v) through the soil

pores to the pressure gradient (dp). For in situ permeability measurement we ap-

plied a soil probe that was designed and made at the INP, PAS. Because perme-

ability depends on velocity we calibrated our probe in laboratory conditions. For

calibration we applied semi-empirical formula for permeability, depending on

porosity, particle-size and soil water saturation fraction. We used two types of

sand, because it is almost isotropic and homogenous medium.

As a result we obtained formula for shape coefficient W depending on v (velocity

of fluid flow). The formula is a polynomial regression

2 31 2 3W A B v B v B v= + + +

where A and B are constants. For calculating permeability we use the following

term

[ ]/k W v dp= .

Page 75 of 199


Page 76 of 199


INFLUENCE OF METEOROLOGICALCONDITIONS ON RADON MEASUREMENTS

IN SOIL – PRELIMINARY RESULTS

Jadwiga Mazur, Krzysztof Kozak, Tomasz Horwacik, RyszardHaber, Tadeusz Zdziarski


Sciences, PL-31-342 Kraków, Radzikowskiego 152 St., POLAND


Radon concentration in soil gas and its exhalation rate from the ground are very

important factors that influence on indoor radon concentration and, in conse-

quence, human health. Both these quantities depend not only on soil parameters

(e.g. porosity, humidity, permeability, radium content, etc.) but on meteorological

conditions as well. Since autumn 2003 the systematic measurements concerning

radon exhalation rate from the ground and radon concentration in soil gas have

been performed in the Natural Radioactivity Laboratory on a special “Radon Study

Field” which is located on the Institute grounds. The continuous registration of me-

teorological parameters is also carried on the spot by means of the Weather Moni-

tor II (DAVIS production). The measurements of soil temperature and pressure dif-

ference on 30, 50 and 100 cm depths were performed additionally and the results

were used for checking the influence of those parameters on radon exhalation

rate.

Page 77 of 199


The passive method (CR-39 detectors) and the ionization chamber AlphaGUARD

PQ 2000 PRO (Genitron GmbH) are used for the measurements of radon concen-

tration in soil. The AlphaGUARD gauge together with the special accumulation

container serve for the determination of radon exhalation rate from the ground.

The paper presents the preliminary results of the investigation of the influence of

some meteorological parameters (air pressure and temperature, humidity, precipi-

tation, wind speed and direction) on radon concentration in soil and its exhalation

rate.

Page 78 of 199


METHODS FOR ASSESSMENT OF THEOCCUPATIONAL EXPOSURE AT WORKING

PLACES OF DIFFERENT TENORMINDUSTRIAL BRANCHES

Dietmar Weiß, Harald Biesold, Peter Jovanovic, Lászlò Juhàsz,Ales Laciok, Karsten Leopold, Boguslaw Michalik, Hana Mora-

vanská, André Poffijn, Mihail Popescu, Cornel Radulescu, PávelSzerbin, Jens Wiegand

Within the TENORMHARM project one task concerns an assessment of the radi-

ation dose to workers in different TENORM industries which are of some rele-

vance within the participating EU and candidate countries.

This assessment is based upon information and data collected at the beginning of

the project and, if existing, on national regulations and compared to EU standards.

The most relevant industries of each participating country where TENORM occur

were reported and compared, from which each participant selected one branch

where an occupational exposure of more than 1 mSv/yr could be expected. Sub-

sequently, the calculation of the radiation dose was carried out independently by

each participating country. Also the real situation at the considered working place,

as respiratory protection or indoor air cleaning measures, was considered.

The results of the dose calculation obtained by each contractor for the selected

exposure scenario was compared with the same or a similar scenario described in

Radiation Protection 107. This comparison demonstrated, that the applicability of

International droup carrying out FP–S EURATOM Project „TENORMHARM”Page 79 of 199


reference levels for regulatory control of workplaces given in RP 107 was limited

because the considered scenarios used, do not reflect sufficiently the recent work

conditions. Moreover, any scenarios described by the contractors had no applica-

ble counterpart in RP 107.

The results of this comparison will be presented and proposals for realistic dose

assessments at different working places where TENORM occur will be given.

Acknowledgement:

The work is funded and carried out in the EU 5th FP, Nuclear Fission and Radia-

tion Protection, Contract No FIGM-CT-2001-00174.

Page 80 of 199


DETECTION SYSTEM FOR SURVEY OF THEPROFESIONAL EXPOSED PERSONAL

Ana I. Stochioiu1), Felicia S. Mihai1), Iulia I. Georgescu2)

1) Horia Hulubei – National Institute for Physics and Nuclear Engineering, IFIN-HH,

Bucharest, ROMANIA2) Polytechnic University of Bucharest, ROMANIA

The individual control at the internal and external irradiation is necessary for the

entire personal who work in the nuclear ranges and in all the domains where are

used radiation sources.

In our country, the accredited work for the radiological survey at the external irradi-

ation is for the dosimetric film. In the countries with evolved nuclear activities, the

survey of personal is made with dosimetric film and thermoluminiscent dosimeters

for evaluation as precise as possible of the equivalent dose and her evidence.

The thermoluminiscent multifunctional dosimeter with thermoluminiscent detectors

type TL-100, obtained in our department, respectively LiF: Mg, Ti is one of the

passive system of detection which can be used for comparing the dosimetric film.

In this paper are presented experimental data compared between the two system

of detection. The data are: the dosimetric answer for different values of dose and

errors of determinations are in acceptable limits.

Page 81 of 199


THE PROPOSAL OF THE SWEDISHCOMMITTEE ON MANAGEMENT OF NON-

NUCLEAR RADIOACTIVE WASTE (IKA) ANDTHE IMPLICATIONS FOR THE MANAGEMENTOF NORM AND STORAGE OF NORM WASTE

Gustav Åkerblom, Nils Hagberg, Lars Mjönes, Ann-Louis Söder-man

Swedish Radiation Protection Authority, SE 171 16 Stockholm, SWEDEN

e-mail: [email protected] [email protected]@ssi.se

The Swedish Government Committee on Management of Non-Nuclear Radioac-

tive Waste (IKA) has the commitment to propose regulations regarding NORM to

be included in the Swedish Radiation Protection Law and the Radiation Protection

Ordinance.

The production, handling and waste storage of such products has earlier not been

subject to legal regulations, but is now to be included in the Radiation Protection

Law and Ordinance.

Waste that will be subject to the new regulations are for example, ashes contain-

ing NORM and ashes of biofuel containing cesium-137 from the Chernobyl acci-

dent, uranium-rich skarn from mining of iron ores (even if the mine was aban-

doned many years ago), gypsum waste from phosphate production, alum shale

burnt to extract oil (there exist more than 50 million m2 of such material), filters andPage 82 of 199


sludge from water treatment equipment and pipes and pumps contaminated with

radium due to precipitation from water.

The Committee proposes that the producer that utilizes raw material containing

naturally occurring radioactive substances shall have the full responsibility for fu-

ture depositing of the waste. The responsibility shall include a fee to a new Gov-

ernment fund to cover the total costs for management and future storage of the

waste. This fee is to be paid by the producer of the waste material.

In case the waste consists of material from old use of natural radioactive material

with no present owner, e.g. uranium use for colouring ceramics, the fund may in

some cases cover the cost. This might also be the case when the disposal costs

are unreasonable high for a private person, e.g. for disposal of resins used for

treatment of water, which is contaminated with so high concentrations of uranium

or radium that it has to be handled as radioactive waste. Radioactive waste from

old abandoned mines, e.g. uranium mineralised waste rock at old iron mines or

alum shale excavations were no present owner has the responsibility for the waste

are proposed to be regarded as contaminated sites and thus entitled to the same

Government funds that are used for restoring land contaminated by chemical sub-

stances.

Page 83 of 199


SEQUENTIAL EXTRACTION OF URANIUMISOTOPES IN SEDIMENTS FROM AN

ESTUARY HISTORICALLY AFFECTED BYANTHROPOGENIC INPUTS OF NATURAL

RADIONUCLIDES

Juan L. Aguado11), Juan P. Bolívar1), Rafael García-Tenorio2)

1) Departamento de Física Aplicada, Universidad de Huelva, Facultad de

Ciencias Experimentales, Campus de El Carmen, 21071 Huelva, SPAIN2) Departamento de Física Aplicada II, Universidad de Sevilla, E.T.S.A., Avda.

Reina Mercedes 2, 41012 Seville, SPAIN


Riverbed sediments collected from an estuary historically affected by several an-

thropogenic activities, particularly by uranium-series radionuclides enriched

wastes discharged by several phosphate fertiliser plants, have been operationally

speciated using a Tessier-based selective-leaching procedure. 234U and 238U con-

tent in each selective fraction were determined by alpha-particle spectrometry af-

ter radiochemical isolation and electrodeposition onto stainless steel planchets.

These studies were performed in the uranium-polluted estuarine sediments one

year after the phosphate fertiliser discharges stopped. The aim of this work was to

obtain useful information about the operational forms in which this element re-Page 84 of 199


mains associated with the sediments at this time. Our results show a significant

fraction of uranium radionuclides associated to operational forms that could be re-

lated to weak forms of adsorption to the sediments. Consequently, it is possible to

foresee a potential remobilisation of uranium contamination from sediments to the

aqueous phase in the future under normal environmental conditions.

Keywords: U-isotopes, -particle spectrometry, speciation, sediments, TENORM.

Page 85 of 199


ASSESSMENT OF THE RADONCONTRIBUTION FROM MINING SITES TO

THE GEOGENIC ENVIRONMENT

R. Rolle

Goettingen, GERMANY

An issue of NORMs in mining areas is the mean ‘Rn-exposure’ assignable to sur-

face mining residues. Outdoor Rn-decay product concentrations (at breathing

height), compared with elevated indoor levels, are relatively low and they fluctuate

widely with time and location. Differentiating a mining contribution of ‘Rn-exposure’

from a geogenic exposure is a challenging metrological task, particulary in the lat-

er stages of remediation. The interacting vertical and horizontal atmospheric air

exchange and the Rn exhalation, largely varying with moisture content of the

ground, cause widely varying Rn concentration patterns that are influenced by the

weather on short and long timescales. The combined effect of varying source and

of varying air exchange can be split into its components by time-resolved concen-

tration measurement of the decay chain members of Rn, since at a given time the

local ratios of concentration of the chain members are a function of the air ex-

change only. From the actual concentrations and the air exchange the source

term can be calculated. The concentrations of the short-lived decay products of

Rn can be measured continuously far more accurately per unit time than the Rn

gas concentration. The Rn decay product ratios, and thus air exchange rates, can

be assessed continuously with a time resolution of the order of 30 minutes or less.

Page 86 of 199


Since the main exposure contribution derives from a few high, short-lived expo-

sures, accurate time-resolved measurement of Rn decay product concentrations

offers the optimal metrology for differentiating Rn-exposure contributions. True in-

strument calibration and minimal entrance losses in the decay product measure-

ment are a requisite for attaining acceptable accuracy with an otherwise only

roughly defined environmental source/sink compartment model.

Page 87 of 199


NEW REGULATORY DEVELOPMENTS ANDGUIDANCE IN THE EU WITH REGARD

TO NORM

T.P. Ryan, A. Janssens, E. Henrich, J.L. Daroussin

European Commission, DG TREN, H4, Radiation Protection, Rue Alcide de

Gasperi, Bâtiment Wagner, L-2920 LUXEMBOURG

A framework for a regulatory system for the control of exposure of workers and

members of the public to natural radiation sources was introduced in Council Di-

rective 96/29/EURATOM 13 May 1996. The directive deals with basic safety stan-

dards for the protection of the health of workers and the general public against the

dangers posed by ionising radiation. In particular Title VII of the directive deals

with significant increases in exposure due to natural radiation sources. This ap-

plies to “work activities” or industries within which the presence of natural radiation

sources leads to a significant increase in the exposure of workers or members of

the public and which cannot be disregarded from the radiation protection point of

view. In accordance with Articles 40 and 41 of the directive, each Member State is

directed to ensure the identification of such work activities and to setting-up the

appropriate means for monitoring exposure and applying radiation protection mea-

sures as set out in the directive.

To assist Member States with the implementation of the directive in general and

Title VII in particular, the Commission has published a number of guidance docu-

ments. However, no guidance has yet been developed in relation to discharges

Page 88 of 199


from NORM industries. In order to begin to address this, a study was carried out,

the results of which have now been delivered. The aims of this study were: to re-

view the regulatory framework within Member States regarding the implementation

of Title VII of the directive with respect to effluent discharges; to provide guidance

for a realistic dose assessment methodology for NORM discharges and to estab-

lish criteria allowing the rapid identification of effluent discharges potentially requir-

ing regulatory control. The results of this study will be considered by the Group of

Experts established under Article 31 of the Euratom Treaty with a view to advising

the Commission on appropriate guidelines.

In addition, the Commission has awarded a contract with a view to developing a

Network for stakeholders involved in NORM issues to share experience and to

build a common understanding of the inherent problems and workable solutions.

The Network will aim to identify and promote good practice, to enhance risk

awareness and to create a common risk culture between stakeholders. It will act

as an archive for relevant documentation that will be available to the members of

the Network.

Page 89 of 199


INDUSTRIES GIVING RISE TO NORMDISCHARGES IN THE EU – A REVIEW

T.P. Ryan1), A. Janssens1), E. Henrich1), J.L. Daroussin1), Z.K.Hillis2), E.I.M. Meijne3)

1) European Commission, DG TREN, H4, Radiation Protection, Rue Alcide de

Gasperi, Bâtiment Wagner, L-2920 LUXEMBOURG2) NNC Limited, The Renaissance Centre, 601 Faraday Street, Birchwood

Park, Warrington, Cheshire, WA3 6GN, ENGLAND3) NRG, PO Box 25, NL-1755 ZG Petten, THE NETHERLANDS

The focus of this paper is the identification of industries giving rise to discharges

or residues of naturally occurring radioactive material (NORM) that are potentially

significant in terms of public exposure and therefore may require regulatory control

as set out in Title VII of EU Council Directive 96/29/Euratom (Basic Safety Stan-

dards Directive). The industries have been identified and assessed as part of a

study commissioned by the European Commission with a view to assisting Mem-

ber States in implementing the aforementioned Directive in this area. Information

was gathered largely on the basis of data supplied by regulatory authorities in

Member States by means of a questionnaire as well as through published reports

and direct contacts with organisations such as trade associations. It is evident that

available information on wastes and discharges both in terms of volume and con-

tent are limited. Furthermore, there are few reliable monitoring data for radioactive

substances probably as a consequence of the absence of previous regulatory

control.Page 90 of 199


The industries studied in this paper include: fossil fuel power stations; oil and gas

extraction; metal processing; phosphate processing and production; titanium oxide

pigment production; rare earth processes and cement production. A brief descrip-

tion of the processes involved in each is presented including an analysis of the

waste production pathways, activity concentrations, typical emissions and annual

throughput, where available. It is noted that characteristics of discharges and

residues, even from the same type of industry and production process, have been

found to differ widely because of the variation in raw material used and processing

methods. This is particularly pertinent in respect of differences in treatment of liq-

uid wastes and off-gases prior to discharge.

It is possible that for some of the NORM industries studied, controls already in

place to prevent non-radioactive pollution may have the additional benefit of con-

trolling the radioactive discharges. However it must also be highlighted that re-

stricting discharges may increase the amount of radioactivity retained in residues

such as sludge and dust.

Page 91 of 199


THE RAPID IDENTIFICATION OF NORMDISCHARGES REQUIRING REGULATORY

CONTROL – A POSSIBLE SCREENINGMETHODOLOGY

E. Henrich1), A. Janssens1), T.P. Ryan1), J.L. Daroussin1), K.R.Smith2), M.Y. Gerchikov3)

1) European Commission, DG TREN, H4, Radiation Protection, Rue Alcide de

Gasperi, Bâtiment Wagner, L-2920 LUXEMBOURG2) NRPB, Chilton, Didcot, Oxon, OX11 0RQ, ENGLAND

3) NNC Limited, The Renaissance Centre, 601 Faraday Street, Birchwood

Park, Warrington, Cheshire, WA3 6GN, ENGLAND

The European Commission (EC) is mindful of the potential difficulties for national

regulators in implementing a process of regulatory control as set out in Title VII of

EU Council Directive 96/29/Euratom (Basic Safety Standards Directive) for NORM

industries discharging into the environment. As a consequence, the EC commis-

sioned a study to identify possible procedures for the rapid identification of such

industries or work activities where members of the public are potentially exposed,

with a view to producing guidelines. The results of the study are presented in this

paper.

It is well understood that there is no simple relationship between discharge rate

from

a NORM industry and dose to members of the public. However, with respect toPage 92 of 199


regulatory control, a detailed site-specific analysis may not be warranted when, on

the basis of a conservative approach, it can be concluded that the discharges are

of no radiological significance. This introduces the idea of NORM discharge

screening levels which may be defined as estimates of the amount of activity dis-

charged to the environment, which, if not exceeded, mean that it is very unlikely

that members of the public would receive an effective dose above a defined dose

criterion. NORM discharge-screening levels can be defined for each NORM re-

lease route and would be calculated using deliberately cautious assumptions. The

derivation of such screening levels would comprise the following steps: definition

of reference discharge situations; choices of models, exposure pathways and pa-

rameters; derived doses per unit discharge rate; dose criteria for screening levels

and finally, discharge screening levels.

In this paper, discharge-screening levels are derived and presented. It is unlikely

that below these levels a more detailed site-specific radiological assessment of

the discharges would be warranted. It is recommended that a dose criterion be

chosen for the screening level that is below the dose constraint for the facility. If

discharge-screening levels are exceeded it is recommended that regulatory bod-

ies verify the actual level of discharge, re-examine discharge conditions such as

stack height or river flow, re-examine the existence of assumed exposure path-

ways and decide on the need for site-specific assessment.

Page 93 of 199


POLISH NATIONAL INTERCOMPARISONS OFMEASUREMENT METHODS OF 222RN

CONCENTRATION IN WATERS

Tadeusz A. Przylibski1), Kalina Mamont-Cieśla2), Olga Stawarz2),Barbara Kłos3), Jerzy Dorda3), SPI Team4)

1) Wrocław University of Technology, Faculty of Mining, Division of Geology

and Mineral Waters Wybrzeże S. Wyspiańskiego 27, 50-370 Wrocław, POLAND,


2) Central Laboratory for Radiological Protection, Dosimetry Department,

Radon Dosimetry Group ul. Konwaliowa 7, 03-194 Warsaw, POLAND3) University of Silesia, Institute of Physics, Department of Nuclear Physics

and Its Application ul. Uniwersytecka 4, 40-007 Katowice, POLAND4) Staff from all Participating Institutions: Wrocław University of Technology –

Anna Adamczyk; Central Laboratory for Radiological Protection – Monika Kusyk;

University of Silesia – Beata Kozłowska; Central Mining Institute – Małgorzata

Wysocka, Stanisław Chałupnik, Antoni Mielnikow; The Henryk Niewodniczański

Institute of Nuclear Physics of the Polish Academy of Sciences – Krzysztof Kozak,

Mirosław Janik, Elżbieta Kochowska, Jadwiga MAZUR; Medical School of

Białystok – Maria Karpińska; Nofer Institute of Occupational Medicine – Zbigniew

Kamiński; AGH University of Science and Technology – Nguyen-Dinh CHAU;

Lądek-Długopole S.A. Health Resort – Bogdan Ciekot; Analytical Laboratory from

Świeradów Zdrój – Katarzyna Kania; Private Laboratory from Szczawno Zdrój –

Zdzisław Rafalski.

Page 94 of 199


The results of intercomparison measurements of 222Rn concentration in the water

samples are presented. In the above mentioned measurements generally 11 labo-

ratories from many Polish research and commercial institutions took part. Seven

of them partycipated in

3 intercomparison measurements organized in the years 2001–2003. In the years

2001 and 2002 the intercomparison measurements were carried out in the Sudety

Mountains (Szczawno Zdrój and Świeradów Zdrój health-resorts, respectively).

During these two experiments water samples were taken from mineral springs,

considered in Poland as medicinal ones. They are characterized by increased CO2

concentration (1.56–2.07 g/dm3), as well as different values of total dissolved

solids (TDS between 0.18 and 2.97 g/dm3), radon concentration (between 9 and

985 Bq/dm3) and other distinct differences in chemical composition and physical

properties.

In 2003 experiment measurements were carried out in water samples prepeared

in CLOR in Warsaw. The samples were produced by the aeration of a 10-dm3

container full of tap water with air enriched by 222Rn coming from a PYLON source

(502.5 kBq activity of 226Ra). During all intercomparison experiments the concen-

tration of 222Rn for 7 water samples (2, 3 and 2 in 2001, 2002 and 2003, respec-

tively) was determined. Special care was taken to ensure the same conditions of

collecting the water samples for each participant.

The laboratories participating in the experiments were applying different tech-

niques to determine the concentration of 222Rn in the water samples: a liquid scin-

tillation method, gamma detectors, Lucas cells and ionisation chambers.

The obtained results confirmed that keeping the containers with water samples

closed tightly from the moment of collecting till the measurements was of a great

importance.

It happened twice, in the different laboratories that a leakage in the measurement

set-up (in the AlphaGUARD™ + AquaKIT™ system) resulted in the determination

of lowered values of 222Rn concentrations. The best consistency of the results in

all 3 intercomparison measurements was obtained by the laboratories using the

Page 95 of 199


liquid scintillation method. It has been observed, that the number of laboratories

that got consistent results (within error limits) is increasing from 55% in 2001 to

75% in 2003. This confirms the fact that the organised experiments meet the main

task – improving the correctness of the results obtained in particular laboratories.

Thus, it is necessary to organise such experiments in next years.

The intercomparisons in 2002 and 2003 were organized within the confines of the

activity of the Radon Centre and with its financial support.

Page 96 of 199


APPLICATION OF INTERNATIONAL SAFETYSTANDARDS TO WORK INVOLVING

EXPOSURE TO NATURAL RADIATION

Denis Wymer

International Atomic Energy Agency P O Box 100, A-1400 Vienna, AUSTRIA


One of the statutory functions of the International Atomic Energy Agency (IAEA) is

to establish standards of safety for protection against ionizing radiation and to pro-

vide for the application of these standards to peaceful human activities. The Inter-

national Basic Safety Standards for Protection against Ionizing Radiation and for

the Safety of Radiation Sources (the BSS), published by the IAEA in 1996 and co-

sponsored by several other major international organizations, contain the basic re-

quirements to be fulfilled in all activities involving radiation exposure, including ex-

posure to radiation of natural origin. In developing supporting standards and prac-

tical guidance on the application of the BSS, the IAEA has given progressively

greater attention to exposure arising incidentally from work involving raw materials

containing natural radionuclides. This paper describes the direction that this pro-

gramme is taking in response to the needs expressed over the past few years by

participants in various international meetings and conferences organized by the

IAEA. A need has been identified for more data on activity levels, exposures and

doses, as well as the factors influencing these parameters and governing the rela-

Page 97 of 199


tionships between them in specific industrial processes involving naturally occur-

ring radioactive material (NORM). Various data-gathering initiatives are described,

including the gathering, interpretation and reporting of existing, reliable data for

specific NORM industrial processes, and the formulation of a Co-ordinated Re-

search Programme starting in 2004 to gather new data. A need has also been

identified for practical guidance on the establishment of national systems of con-

trol over exposures to natural radiation, taking into account the very wide range of

exposure scenarios and the necessity for pragmatism – that is, for radiation pro-

tection to be optimized to ensure that the degree of regulatory attention given to

any particular situation is commensurate with what can be realistically achieved.

The paper will describe the progress being made in this area in terms of conclu-

sions to be drawn from existing guidance material, the programme for developing

this guidance further in areas where uncertainties continue to be experienced, and

the dissemination of this guidance in the form of training courses and other activi-

ties.

Page 98 of 199


A SPECIFIC STUDY CONCERNING NORM INREFRACTORIES INDUSTRIES

F. Trotti1), C. Zampieri1), G. Clauser2), M. Facchinelli2), D. Desideri3),G. Jia4), P. Innocenzi4), R. Ocone4)

1) ARPA Veneto – Regional Agency for the Environmental Protection of

Veneto via A. Dominutti 8, 37135 Verona, ITALY

e-mail: [email protected]; [email protected]

2) APPA Trento – Provincial Agency for the Environmental Protection of Trento

Piazza A. Vittoria 5, 38100 Trento, ITALY3) Institute of General Chemistry – Urbino University, Piazza Rinascimento 6,

61029 Urbino, ITALY4) APAT – National Agency for the Environmental Protection via V. Brancati

48, 00144 Roma, ITALY

A specific study concerning refractory industries has been performed by a group

of Italian Regional Environmental Protection Agencies together with the National

Environmental Protection Agency. The aim of this study was to evaluate the envi-

ronmental impact for some activities dealing with NORM.

In this frame, all steps of the standard working cycle are described: the beginning

from the raw materials (zircon sands or semi-finished zircon silicates based com-

ponents) and the end up to the finished products and the production of residues,

dust and treatment water. A radiological survey has been carried out in two North-

ern Italy companies.Page 99 of 199


Activity concentrations measurements by gamma spectrometry (more relevant

gamma nuclides of natural chains) and radiochemical analysis (210Pb, 210Po) on

raw materials, finished products, residues and treatment water were made.

Information and technical data related to the present working cycle have been col-

lected by means of specific questionnaires, sent to most of the involved factories

selected from the sector association’s data base.

An estimate of the environmental pressure from the two companies and the whole

sector itself is assessed by the combination of the radiological results of two com-

panies survey with information from the questionnaires.

Page 100 of 199


GRAIN SIZE IN RADIOMETRICMEASUREMENTS OF GROUND

V. Gablin

Moscow Scientific-Industrial Association „Radon” 2/14, 7th Rostovsky per.,

Moscow 119121 RUSSIA


Known procedures of radiometric measurements of ground differ significantly in

grain size of the sample. The range is 0.043–0.25 mm. To answer the question

about the proper grain size of the sample to be measured one must address to the

three types of radioactivity in grounds.

Natural radioactivity is distributed homogeneously through the bulk of sample. It is

either nuclides in crystal structure of minerals (K in KAlSi3O8) or isomorphic re-

placement in crystal structure (Ra in BaSO4, Th in ZrSiO4, U in CePO4). Model ra-

diometric measurements of the same sample with grain size ranging from 0.125

mm to 2 mm do not show significant difference between specific α- and β-activi-

ties in spite of increasing of specific surface. That is why there is no reason to

grind monocrystal grains.

Artificial radioactivity is caused by atmospheric fallout presenting nuclides in dy-

namic form, or by “hot particles” which are commonly uranium and plutonium ox-

ides (silicates) and also 14C. If we grind “hot particle” its fine subparticles will cover

non-active grains of matrix that will lead to increasing of surface contamination

and as a result – to increasing of specific radioactivity.Page 101 of 199


Secondary radioactivity is a result of changes of nuclides concentration in grounds

owing to weathering, infiltration, precipitation and other natural processes. Both

natural and artificial nuclides can be involved in these processes. Nuclides here

occur preferentially in sorbed form on the grain surface as salts, hydroxides and

complex compounds. This is another kind of inhomogeneity, not so sharp one.

Grinding such grains increases specific surface, decreasing specific radioactivity.

Thus the whole bulk of sample to be measured should be driven to monocrystal

state, i. e. grain size does not have to be definite. In case if the sample of ground

contains “hot particles” one must try to separate it to active and non-active parts

as carefully as possible with two different subsequent measurements.

Page 102 of 199


TEST THRESHOLDS FOR ASSESSMENT OFPOSSIBLE GROUNDWATER CONTAMINA-TION AT SITES CONTAMINATED WITH RA-

DIOACTIVE MATERIALS

Rainer Gellermann1), Michael Hahn, Ulrike Haberlau, JoachimBeetz2)

1) HGN Hydrogeologie GmbH, Waller Weg 22, D-38112 Braunschweig phone:

++49 531 23170300, GERMANY


2) Landesamt für Verbraucherschutz und Landwirtschaft Brandenburg,

Postfach 1370, D-15203 Frankfurt (Oder), phone: ++49 335 560 0, GERMANY


At several sites in Land Brandenburg the ground is contaminated with natural ra-

dionuclides, especially thorium from former industrial processes. Such type of

contamination is regulated neither in the Federal Ordinance on Soil Protection and

Contaminated Sites (BBodSchV) nor in the German Radiation Protection Ordi-

nance (StrlSchV). However, the European Basic Safety Standards Directive speci-

fies that areas of former practice or work that are a source of permanent risk to

people have to be demarcated and controlled. If necessary, intervention measures

need to be carried out and access must be restricted. Therefore treatment of such

Page 103 of 199


cases requires technical regulations and supporting instructions to facilitate cor-

rect decisions by the relevant authorities. Such regulations must be conform with

the existing regulations, especially the BBodSchV and guidelines of urban land

use planning.

When assessing existing situations, the exposure path “groundwater” is of particu-

lar significance for any decision-making. In a study suitable criteria and instruc-

tions were derived in order to identify for this special path those areas that can be

considered as uncontaminated and therefore exempt from further radiological in-

vestigations and from any restrictions concerning land use planning. The methodi-

cal approach used corresponds to the leachate forecast according to BBodSchV

as applied for natural radionuclides.

Threshold values were derived from the relation between contamination of soil

and resulting ingestion doses for children younger 1 year. The lower threshold

“UWB” corresponds to a dose level of 0.1 mSv/a, the upper one “OWB” corre-

sponds to 0.5 mSv/a. The following test thresholds “UBW” were obtained for a

contamination close to or in contact with groundwater:

40 Bq/kg for the maximum activity of 232Th decay chain;

40 Bq/kg for maximum activity of 238U chain.

If the contamination is located significantly higher than the groundwater table

(here: more than 1 m), then the values are:

1000 Bq/kg for the maximum activity of 232Th decay chain,

200 Bq/kg for maximum activity of 238U chain.

Page 104 of 199


NATURAL RADIOISOTOPE LEVELDIFFERENTIATION IN ARABLE AND

NONCULTIVATED SOILS AT ŁĘCZNA-WŁODAWA LAKE DISTRICT

A. Komosa, St. Chibowski, J. Solecki, M. Reszka

Department of Radiochemistry and Colloid Chemistry, Maria Curie-Skłodowska

University, Pl. M. Curie-Skłodowskiej 3, 20-031 Lublin, POLAND


Pojezierze Łęczyńsko-Włodawskie district located on East of Poland is used as

recreation ground but mainly it is an agriculture area producing ecological food.

Due to lack of industry this area is relatively low contaminated. An exception is

Bogdanka coal mine located 20 km north of Łęczna town at vicinity of Poleski Na-

tional Park. Its activity, despite of the law and technical regulations observance

may be disadvantageous for the environment in future. A potential hazard may

give accumulation of natural radioactive elements in soil and bottom sediments,

which results from increase of the storage field (up to 83 ha in future) and disposal

of coal mine water to the Świnka river.

In the paper the comparison studies of the concentration of some natural radioac-

tive isotopes in cultivated and unploughed area are presented. The samples were

collected from 0–10 cm surface layer at seven points at Poleski National Park bor-

Page 105 of 199


der. Concentration of gamma radioactive isotopes was measured by Silena-Can-

berra semiconductor (HPGe) spectrometer with Genie-2000 software for quantita-

tive analysis of the nuclides. Obtained results enable estimation of health hazard

by natural and anthropogenic 137Cs gamma radioactive isotopes.

Page 106 of 199


ATTEMPTS ON RADON EXHALATION RATEDETERMINATION FROM A WASTE-DUMP AT

THE BOGDANKA COAL MINE USING THEPICORAD DETECTORS

A. Komosa1), St. Chibowski1), St. Chałupnik2)

1) Department of Radiochemistry and Colloid Chemistry, Maria Curie-

Skłodowska University, Pl. M. Curie-Skłodowskiej 3, 20-031 Lublin, POLAND


2) Central Mining Institute, Pl. Gwarków 1, 40-166 Katowice, POLAND

Bogdanka coal mine is located in Pojezierze Łęczyńsko-Włodawskie district at

vicinity of Poleski National Park. From the beginning of the coal mine activity i.e.

for 20 years waste rock is deposited close by. It mainly consists of clumps (about

88%) of a few centimeters grain-size, whereas sandstones, siderite and mud-

stones form the rest. Storage yard filled in about 30 percent covers 83 ha and is

cultivated in part.

It is well known that deposited waste rocks of coal mines may be a source of

radon.

The emission rate of this element from a spoil dump depends on many factors so

direct measurements of an exhalation rate are the most reliable.

Page 107 of 199


Passive detectors containing activated carbon, Picorad (Niton-Canberra-Packard),

designed to the detection of indoor radon at stable concentration of this nuclide

were used. An application of these detectors in open area may produce errors

connected with higher humidity and varied concentration of exhaled radon.

The radioactivity of radon and its daughters was determined with liquid scintillation

spectrometer by Quantulus (Wallac-Perkin-Elmer). Measurements were made in

several points of the spoil dump including last deposited and cultivated sites. A

calibration of the detectors with various concentrations of radon and humidity level

was performed in a radon chamber in Central Mining Institute.

Page 108 of 199


DETERMINATION OF 210PO AND 210PB FROMMARINE SEDIMENTS

Paula Juntunen, Maria Betti

European Commission, Joint Research Centre, Institute for Transuranium

Elements, P.O.Box 2340, 76125 Karlsruhe, GERMANY


The sediments of the northeast Irish Sea are radioactively contaminated due to

controlled discharges of low-level radioactive waste from nuclear facilities. Our

core samples have already been well profiled with respect to U, Np, Am and Pu.

The concentrations of these nuclides can be compared to Sellafield discharge

declarations. In order to date the sediments, however, we must determine other

radionuclides. The so-called 210Pb method is widely used to determine the accu-

mulation rate of sediments in lakes, oceans and other waters. The age of sedi-

ment from a certain depth in a sediment core can be established from the accu-

mulation rate. This paper describes the determination of 210Po and 210Pb with dif-

ferent methods. By experimentally comparing analytical methods we have chosen

the one that is least time consuming and which has the best analytical figure of

merit. Moreover, the core sediments have been dated and the results compared

with the yearly discharge declaration of the facility.

Page 109 of 199


COSMOGENIC 22NA AND 7BE IN GROUNDLEVEL AIR

Sylwia Grabowska, Jerzy W. Mietelski

The Henryk Niewodniczański Institute of Nuclear Physics Polish Academy of

Sciences, PL-31-342 Kraków, E. Radzikowskiego 152 St., POLAND


The cosmogenic radionuclides are produced in whole atmosphere, although the

most intense processes goes in the stratosphere. One of such radionuclide is22Na, which decays by beta plus decay with half-life-time of 2.6 year, end emits

gamma radiation of 1275 keV. Another one is 7Be, which is also gamma-emitter

(478 keV) and which half-life time is 54 days. Sooner or later all not gaseous mat-

ter attaches to the aerosols. From stratosphere cosmogenic radionuclides migrate

to ground level air by means of different processes like diffusion, sedimentation,

convection. Usually on ground level air the activity of 22Na is on the level of a frac-

tion of single Bq/m3 may be studied by filtration of high volumes of the air and ap-

plication of low-level gamma spectrometry. 7Be is much more active, on the level

of few mBq/m3.

The Petryanov air filters from two ASS-500 aerosol sampling stations in weekly

achieved sets exposed in Krakow during 2003 are analyzed for the presence of all

gamma-emitters using a gamma-rays spectrometer with HPGe detector shielded

with complex active and passive shields. Each sample contains aerosols from

more than 0.1 Mm3 of air. In our previous study covering years 1996–2002 (in halfPage 110 of 199


a year sets of samples) the cosmogenic 22Na shows a strong seasonal variation

with significant different mean values activity concentration between 0.3330.095

Bq m-3 and 0.1370.045 Bq m3, for summer and winter, respectively [1]. More-

over, the activity ratio for two cosmogenic radionuclides: 22Na and 7Be showed

also changes with statistically significant seasonal differences. The lower values

were found during winters. The conclusion was that transport of 22Na from strato-

sphere to ground level air during summer seems to be so much effective, that re-

sult in kind of relative depletion of stratosphere of this nuclide. The aim of present

investigation is to see the changes of 22Na activity and of 22Na to 7Be activity ratio

in more detailed way within a year period.

References

S. Grabowska, J.W. Mietelski, K. Kozak, P. Gaca, Gamma emitters on micro-bec-

querel activity level in air at Kraków (Poland), Journal of Atmospheric Chemistry

(2003), vol. 46, p. 103-116.

Page 111 of 199


APPLICATION OF LIQUID SCINTILLATIONCOUNTING TECHNIQUE TO GROSS ALPHA,

GROSS BETA AND RADON MEASUREMENTSIN PORTUGUESE WATERS

I. Lopes, M.J. Madruga, F.P. Carvalho

Nuclear and Technological Institute, Department of Radiological Protection and

Nuclear Safety Estrada Nacional 10 (Apartado 21) 2686-953 Sacavém,

PORTUGAL


Natural water contains a number of alpha and beta emitters and the radiological

examination such as the determination of the quality of drinking water requires

measuring of mixtures of and emitters. The recommendation of Portuguese

law proposed limits values (0.1 Bq/l and 1 Bq/l) for gross alpha and gross beta ac-

tivities, respectively. The main goal of this work was to develop, test and optimise

new radiometric techniques for measuring mixtures of and emitters in drinking

waters. Liquid scintillation counting technique (LSC) has been optimized for the

determination of these radiological parameters. We used a low background liquid

scintillation system detector with the ability to discriminate between alpha and beta

particles by pulse shape analysis (PSA). High counting efficiencies and lower lim-

its detection were obtained. The first studies on the radioactivity content of some

Page 112 of 199


bottled waters showed the limits values weren’t exceeded. Water samples from

taps, wells and springs have already been collected in old mining areas for further

analysis. The results of gross alpha and beta measurements showed waters with

more high activities.

This water samples collected in that areas are also enriched with dissolved Rn,

produced in rocks containing uranium. Radon levels were determined by short

lived daughter products using the LSC technique. The counter was calibrated with226Ra standard solutions, measured one month after and corrected to correspond

secular equilibrium of 226Ra with 222Rn. The counting efficiency was closer to theo-

retical maximum expected (500%). The LLD value for radon measurements was

0.195 Bq/l using the counting time of 60 min. Preliminary results will be described.

Page 113 of 199


EXAMINING THE NATURAL RADIOACTIVITYOF WATER SOURCES TO EVALUATE THE

IMPACT ON SURROUNDING COMMUNITIES

A. Faanhof 1), P. Kempster2)

1) Atomic Energy Corporation of South Africa, PO Box 582, Pretoria, 0001,

REPUBLIC OF SOUTH AFRICA2) Institute for Water Quality Studies, Private Bag X313, Pretoria, 0001,

REPUBLIC OF SOUTH AFRICA

Natural occurring radioactive materials (NORM) are quite common in the South

African mining and mineral processing industry, even so that uranium is produced

as a by-product at certain gold and copper mining sites. Other major industries as-

sociated with NORMs are the coal, copper and heavy mineral sectors.

Legislation in South Africa addresses the allowed yearly radiation dose to regis-

tered radiation workers and the general public, and adheres to the most common

internationally accepted standards of 20 mSv/a and 1 mSv/a respectively for these

categories. The yearly dose is obviously the sum of the contributions from every

individual nuclide from all possible sources. Accordingly, for members of the pub-

lic, the individual sources are to be evaluated at the (South African) guideline level

of 25 μSv/a. This imposes severe constraints on the radioanalytical laboratory to

offer an affordable routine service due to the required sensitivity to analyse these

NORMs and the variety of matrices involved.

Page 114 of 199


Determination of all required parameters to evaluate the yearly dose is possible,

although costly. Correlations of yearly dose with one or two chemical/radionuclide

components will allow an affordable monitoring strategy. According to the evalua-

tion of a survey performed in one of the gold-mining catchment areas in South

Africa this seems indeed possible.

Page 115 of 199


THE UK

K.R. Smith*, S.M. Warner Jones, W.B. Oatway, J.A. Jones, M.P.Harvey, P.V. Shaw,

S.F. Mobbs

National Radiological Protection Board, Chilton, Didcot, Oxon OX12 9XW,

UNITED KINGDOM

*author for correspondence – e-mail: [email protected]

As part of its periodic review of radiation doses to the population of the United

Kingdom, the National Radiological Protection Board identified the need to esti-

mate the radiological impact of the operation of non-nuclear industries which use

or produce materials containing enhanced levels of naturally occurring radionu-

clides. A number of industries have been considered in the study. These include:

coal-fired electricity generation; the steel production industry; the oil and gas in-

dustry; and rare earth industries. For each industry the radiological impact of the

primary industry, the waste streams produced and, where applicable, the use of

by-products were addressed. Doses to workers in the industries and members of

the public were estimated as part of the study.

Page 116 of 199


RADIONUCLIDE CONTAMINATION OFSURFACE WATERS, SEDIMENTS, AND SOIL

CAUSED BY COAL MINING ACTIVITIES INTHE RUHR DISTRICT (GERMANY)

Simone Schmid, Jens Wiegand

The discharge of highly mineralised mine waters with enhanced 226Ra and 228Ra

activity concentrations has affected creeks, rivers, sediments, soils, and plants

along the Lippe River and its tributaries. 226Ra activity concentrations were elevat-

ed in all water samples receiving mine water, with activity concentrations gradually

decreasing with increased distance from the colliery due to dilution and chemical

precipitation of radium with barium. Increased concentrations of radium and radi-

um decay products were also measured in sediments and flood-affected soils.

The sediments show an enrichment of 226Ra up to a factor of 750, while the con-

taminated soils “only” reach a factor of 10. In aquatic plants, a 4-fold increase in226Ra activity concentrations was measured downstream of the discharge points.

The contamination of the river banks and adjacent floodplain with radium is re-

sponsible for enhanced gamma dose rates, which, along with the incorporation of

soil by playing children, provide potential radiation exposure to the public.

Page 117 of 199


PRESENCE OF NORM IN THE CZECHREPUBLIC

H. Moravanska, A. Laciok

Nuclear Research Institute Rez (NRI), CZECH REPUBLIC


NRI Rez participates in the TENORMHARM project within the 5th EU Framework

Programme. NRI´s effort is focused on evaluation of NORM inventory and assess-

ment of radiation dose and health risks to workers and members of the public.

In case of phosphate fertilisers’ production, three major factories ensure the

Czech consumption at present. Nowadays, generally less radioactive raw materi-

als are used such as yellow phosphorus, phosphoric acid, concentrate of Cola-ap-

atite and AMOFOS. Only the concentrate of Cola-apatite contains higher quanti-

ties of 238U, 226Ra and 228Th (several tens of Bq/kg), but even in this case the result-

ed annual effective dose of workers does not exceed the regulatory limit.

Titanium dioxide pigments are produced only in one factory. Relatively radioactive

ilmenite (approx. 140 Bq/kg of 238U and 80 Bq/kg of 228Th) from Ukraine is used as

the raw material. The final product (rutile-TiO2) contains only negligible quantities

of the mentioned nuclides. The majority of the radioactivity content thus remains in

the various wastes – e.g. the content of 210Pb and 226Ra reaches up to several

1000 Bq/kg in sludges.

Currently, one factory processes zirconium refractory material (EUCOR). Only zir-

conium–containing bricks (with specific activity approx. 1.700 Bq/kg of 226Ra) dis-Page 118 of 199


carded from glass factories are used for production of EUCOR. The current con-

sumption of approx. 200 tons of zirconium input material (bricks) means repro-

cessing of 340.000 kBq of 226Ra.

The coal exploitation and use represents one of the most important industries con-

cerning NORM. The concentration of U in the Czech brown coal varies in the

range 5–16.3 ppm and Th 0.2–30.2 ppm; the hard coal contains 2–9 ppm of U.

The majority of the coal is used for the energy production. The U and Th concen-

trate mostly in the ash and slag (about 20 ppm of Th and <12 ppm of U); the con-

centration of all radioelements in gypsum produced in desulphurisation process is

negligible.

The majority of oil and gas used in the Czech industries is imported from abroad.

Measurements of samples of oil sludge from cleaning of IKL and Druzba pipelines

and from of oil tanks exhibited only negligible concentrations (tenths of Bq/kg) of

all radioelements. The similar range of activity has been found in samples from

domestic oil exploitation.

Evaluation of radioactivity in sludges resulting from the 68 ground and surface wa-

ter treatment installations was performed by NRPI. Average specific activity 200

Bq/kg of 226Ra was identified in ground water treatment sludges.

Page 119 of 199


THE PERIODICAL CHANGES THECONCENTRATION OF INDOOR RADON

Maria Karpińska, Zenon Mnich, Jacek Kapała

Department of Biophysics, Medical University of Białystok Mickiewicza 2A, 15-089

Białystok, POLAND


Radon provides the largest contribution to the effective dose absorbed by the pop-

ulation inhabiting the region of normal radiation background. In Poland, the radon

effective dose is about 39%. The radon concentration in the indoor air undergoes

diurnal and seasonal changes. In order to analyze more accurately radon signifi-

cance in the evaluation of radiological status of the population it is important to im-

prove methods of the annual mean radon concentration evaluation, as the basis to

assess the obtained effective dose.

One-year's radon concentration measurements were performed in 10, previously

chosen, dwelling houses. Buildings qualified to the examination revealed the

radon concentration of above 200 Bq m3. The integral method of Cr-39 trace de-

tectors in diffusive chambers was used in the study. In each building, 3 detectors,

changed every month, were exposed. All the buildings showed seasonal change-

ability in radon concentrations. The ratio of the radon concentrations during one-

month's exposure to the mean annual concentration ranged from 0.16 to 2.35.

Similar ratios were determined for 2-, 3-, and 6-months' exposure. The values of

coefficients equaled from 0.2 to 2.3 for 2-months' exposure, 0.26 to 2.21 for 3-Page 120 of 199


months' exposure, and 0.36 to 1.54 for 6-months' exposure. Most buildings pre-

sented the negative correlation of radon concentration with outside temperature.

However, the positive correlation could be also observed. There was a correlation

of radon concentration with the sizes of atmospheric pressure amplitudes ob-

served in the month's period.

The coefficients of seasonal radon concentration changeability determined for the

examined buildings approximate the annual value of radon concentration based

on 3- or 6-months' exposure. They can be used to assess the mean concentration

with reference to larger groups of houses. Such assessments, unlike short-term

exposure, represent the risk of population connected with radon inhalation. There

cannot be drawn any conclusions, based on determined coefficients, concerning

radon concentration changeability in a given building as, in spite of dominating

tendencies, particular buildings reveal individual changeability schemes.

Page 121 of 199


INTERCOMPARISON OF INSTRUMENTS FORMEASURING RADON AND RADON PROGENY

HELD IN THE CLOR CALIBRATIONCHAMBER*

Kalina Mamont-Cieśla, Olga Stawarz

Central Laboratory for Radiological Protection, ul. Konwaliowa 7, 03-194 Warsaw,

POLAND

Staff from Participating Institutions: Central Laboratory for Radiological Protection

– Olga Stawarz; Wrocław University of Technology – Tadeusz Przylibski, Anna

Adamczyk; Central Mining Institute – Krystian Skubacz, Stanisław Chałupnik; The

Henryk Niewodniczański Institute of Nuclear Physics of the Polish Academy of

Sciences – Krzysztof Kozak; AGH University of Science and Technology –

Nguyen-Dinh Chau; Institute of Nuclear Chemistry and Technology – Jakub

Bartak; National Atomic Energy Agency – Office for Financial Claims of Former

Workers of Uranium Ore Facility in Jelenia Góra – Jerzy Wróblewski

Intercomparisons among radon laboratories are of particular importance because

calibrated standards for radon activity concentration and for radon progeny activity

concentration in air are not available.

An intercomparison exercise for radon and radon progeny instruments was con-

ducted at the Central Laboratory for Radiological Protection (CLOR) from June 9

* This work was partially supported by Radon Center.Page 122 of 199


to 13, 2003 to verify comparability of mainly continuously measuring instruments

for radon and potential alpha energy concentration (PAEC). Seven Polish institu-

tions participated to intercompare ten radon and six PAEC monitors. Among radon

devices there were: six Genitron AlphaGUARD monitors, two Pylon AB-5 moni-

tors, radiometer RMR1 and a radon probe SRDN2. Among PAEC devices there

were five monitors measuring in continuous mode: three T/N Rn WL Meters co-

working with AlphaGUARD monitors, Pylon WLx monitor and Radon Progeny Par-

ticles Size Spectrometer (RPPSS), and one grab sampling device: aspirator SKC

equipped with ALFA unit.

All the instruments were simultaneously exposed in the CLOR big calibration

chamber of the volume of 12.35 m3, in the radon atmosphere in the range from ca.

2500 Bq/m3 to ca. 700 Bq/m3 under controlled different climatic and aerosol condi-

tions. They were changed from normal (45–50%) to very high relative humidity

(95–99%) and in both values of the relative humidity from low ca. 200 CN/cm3 to

high concentrations of condensation nuclei ca. 31 000 CN/cm3. Aerosols were in-

jected from the TSI water generator. The total exposure lasted ca. 44 hours. A val-

ue of radon concentration calculated on the basis of the activity of radium 226Ra in

the certified Pylon flow-through radon generator constituted the reference value

for radon at the beginning of the exposure. Later the average results in four peri-

ods of time from all instruments could be compared only among themselves due

to the loss of radon while walking in and out the chamber.

In the analysis of the PAEC results the spectrometer RPPSS was considered ref-

erence one because it measures radon progeny particle size distribution and ap-

plies it to correct the PAEC value for plateout of small particles upstream in the in-

let of the device.

AlphaGUARD monitors were also compared in the atmosphere of toron in the

small calibration chamber of volume of 0.32 m3. Toron was pumped into the

chamber from the certified Pylon flow through toron generator in closed circuit with

flow of. 1 dcm3/min. The monitors worked as well in the diffusion mode as in flow

mode with different two flows: 0.5 and 1 dcm3/min.

The results of average radon concentrations for all AlphaGUARD monitors indi-

cate very good agreement for the whole exposure time in the big chamber. For six

Page 123 of 199


AlphaGUARD monitors standard deviations of mean values for four selected peri-

ods range from 1 to 2.8% while for all monitors they range from 5.5 to 20%. The

comparison of the means for AlphaGUARDs in toron chamber, where readings

were on the level of below 100 Bq/m3 gave significantly worse results.

The comparison of the PAEC results from T/N Rn WL Meters and Pylon WLx

monitor with the reference value from RPPSS indicate differences in the calibra-

tion factors ranging from 30 to 42% determined in high aerosol conditions (free

fraction of 5%) and the losses of PAEC ranging from 38 to 55% possibly due to

plateout in the inlets of filter holders in the conditions of low aerosols concentra-

tion (free fraction of 62%).

Page 124 of 199


AEROSOL SAMPLING FOR RADIOLOGICALPROTECTION: WHICH PARTICLE SIZE

AEROSOL SAMPLER TO SELECT?

Jean-Pierre Degrange1), Olivier Witschger2)

1) CEPN, BP-48, 92263, Fontenay-aux-Roses, FRANCE


2) INRS, Laboratoire de Métrologie des Aérosols, avenue de Bourgogne, BP

27, 54501 Vandoeuvre-les-Nancy Cedex, FRANCE

Sampling of radioactive aerosols for the purpose of assessing or predicting occu-

pational radiation doses becomes an important issue in the European countries. In

particular, the 96/29/Euratom Council Directive specifies that aerosol sampling re-

sults can be used for assessing the individual dose when the individual in vivo

and/or bioassay methods are not possible or give insufficient results. It precisely is

the case for exposures by inhalation to Naturally Occurring Radioactive Materials

(NORMs), for which bioassay methods may be associated with high detection lim-

its while in comparison traditional aerosol sampling methods may lead to lower de-

tection limits in terms of dose.

A generic method has been developed to facilitate the identification of the particle

size aerosol sampler (following the inhalable, thoracic or respirable convention) to

select for minimising the respective biases between the true and estimated expo-

Page 125 of 199


sure and the true and estimated effective dose associated with exposure by in-

halation to any radioactive compound.

Calculation based on this method have been applied to various radioactive com-

pounds (of different absorption rates and particle size dispersion characteristics)

of the 238U and 232Th natural chains. These calculation have shown that:

- for exposure and effective dose estimates, the sampling efficiency of the sampler

should be known and corrected for,

- for exposure estimates, an inhalable sampler should be chosen,

- for effective dose estimates, the sampler should be chosen according to the ab-

sorption rate of the considered compound, in order to follow as closely as possible

the AMAD dependency of the compound’s dose coefficients:

- a thoracic sampler should be chosen for compounds of slow and moderate

absorption rate,

- an inhalable sampler should be chosen for compounds of fast absorption

rate,

- in absence of (precise) information on the particle size characteristics of

the ambient aerosol, the following default values should be chosen:

AMAD = 5 m, GSD = 2.5.

This paper presents the key elements of the method and the main results of it’s

application to exposures by inhalation to NORMs.

This work was partially supported by the European Commission DG Research

within the framework of the 5th PCRD (SMOPIE project: “Strategies and Methods

for Optimisation of Internal Exposures of workers from industrial natural sources”).

Page 126 of 199


A PROTOCOL FOR DETERMINATION OFNATURAL RADIONUCLIDES

IN THE GEOTHERMAL WATER

Henryk Bem*, Marcin Olszewski, Aneta Kaczmarek

Institute of Applied Radiation Chemistry, Technical University of Lodz, POLAND

*corresponding autor: Institute of Applied Radiation Chemistry, Technical

University of Łódź

ul. Żwirki 36, 90-924 Łódź, POLAND, phone:48-42-6313195


A routine radiometric analysis of the underground water including the geothermal

water is generally limited to the main natural radionuclides. A simplified protocol

for the determination of natural radionuclides in that kind of water has been test-

ed.

Activities of the main radionuclides from 238U and 232Th series in the Uniejów

geothermal water were determined by combining liquid scintillation counting with

α/β separation and γ spectrometry methods. The 222Rn and 226Ra activities were

measured after extraction of radon from 10 ml water samples to 10 ml of Ultima

Gold F scintillation cocktail directly in the 22 ml scintillation vials. The samples

were counted in a new generation portable liquid scintillation counter, Betascout,

without separation of the phases: over the period of 30 days after extraction. The

average values of the specific activities were equal to 2.95 and 0.64 Bq/dm3 for

Page 127 of 199


222Rn and 226Ra, respectively. The 210Po radionuclide before counting was precon-

centrated from 1 dm3 water samples on hydrated manganese oxide and deposited

on silver discs. The discs were immersed in the 10 ml of scintillator and their activ-

ity was measured also by the same method. The average 210Po concentration was

0.052 Bq/dm3. Activity of the remaining radionuclides was determined by γ-spec-

trometry after their preconcentration on the hydrated manganese oxides from 10

dm3 samples. The activities of two radium radionuclides, 224Ra and 226Ra, can be

calculated from their basic γ-lines, whereas 228Ra can be determined from its de-

cay product – 228Ac, and were equal to 0.52, 0.65 and 0.58 Bq/dm3, respectively.

The activities of 210Pb and 238U (234Th) were below the detection limit of the method

equal to 0.03 Bq/dm3. Based upon the obtained results, it can be concluded that

there are not any radiological restrictions for using this water as a heat source or

for balneological purposes. However, it cannot be used as a mineral drinking wa-

ter, because the calculated committed effective dose from its one year consump-

tion exceeds the WHO recommended value of 0.1 mSv.

Page 128 of 199


DETERMINATION OF RADIUM 226RA NUCLIDEIN GROUND-LEVEL AIR

Henryk Bem*, Marcin Olszewski

Institute of Applied Radiation Chemistry, Technical University of Łódź, POLAND

*corresponding author: Institute of Applied Radiation Chemistry, Technical

University of Łódź, Żwirki 36 str., 90-924 Łódź, POLAND

Installation of the Aerosol Sampling Station (ASS) network in Poland offers the

unique opportunity for measuring natural radionuclide concentration in ground –

level air. The ASS-500 collects air aerosols on a filter placed 2 m above the

ground with the air flow about 500 m³ per hour in a weekly cycle and each weekly

filter is submitted for further γ-spectrometry measurements. Unfortunately, be-

cause of slightly higher background levels caused by lead shields in the regions of234Th (238U) and 226Ra γ-lines, an achieved detection limits for direct determination

of these radionuclides are above the usually occurring concentrations

~1–5 μBq/m³. However, in the case of 226Ra, such measurements can be possible

by recounting of the closed (sealed) filters after a one month period, necessary for

establishing of radioactive equilibrium with ²²²Rn and its decay products, particular-

ly γ-emitting radionuclides: 214Pb and 214Bi. The calculated detection and determi-

nation limits (with 10% relative accuracy), according to Currie’s formulas for these

two radionuclides for 160 000 s counting time were: 0.4 and 1.5 μBq/m³, respec-

tively. The observed 222Ra activities during the half year collection period, including

parts of winter and summer seasons, were always above the detection limit and

ranged from 0.5 to 3 μBq/m³. The radium radionuclides are present in ground-lev-Page 129 of 199


el air as

a result of the resuspension of surface soil particles and fly ash emission from

coal burning during winter time. Therefore, on the basis of 226Ra activity measure-

ments in the surface aerosols a rough contribution of the coal combustion to the

total air suspended particulate matter can be calculated, if the specific activities of

this radionuclide in surface soil and fly ashes are known. Using our previously

published data for 226Ra content in the soil and fly ashes for the Lodz region of

Poland, we could appraise that the coal combustion input to the total air suspend-

ed particulate matter ranged from 10 to 80 %.

Page 130 of 199


ENVIRONMENTAL RADIOLOGICALMONITORING IN A NIOBIUM MINING REGION

IN BRAZIL

Marcelo Francis Máduar, Ana Cláudia Peres, Barbara PaciMazzilli

Divisão de Radiometria Ambiental Centro de Metrologia das Radiações Instituto

de Pesquisas Energéticas e Nucleares Av. Prof. Lineu Prestes, 2242 – Cidade

Universitária 05508-000, São Paulo, BRAZIL

corresp. author: e-mail: [email protected]

Mining activities represent a potential source of increment of radiation doses to

which the public are exposed (TENORM). In this paper, a niobium mining plant in

Brazil is approached in respect to its environmental radiological impact. Radionu-

clides from the uranium and thorium decay chains occur in the ore, and some of

them are concentrated during the metallurgic process. Therefore, an environmen-

tal monitoring program was established on a routine basis. The aquatic environ-

ment in the influence area of the plant was assessed by measuring samples of

drinking water, groundwater, river water, and sediment from riverbed. Samples of

atmospheric air were also collected. In the water samples, 226Ra, 228Ra, 210Pb, 238U

and 232Th were determined by total alpha and beta counting after radiochemical

separation and neutron activation analysis. In the sediment samples, 226Ra and228Ra were determined by gamma spectrometry. In the atmospheric air, 222Rn and

Page 131 of 199


its decay products were determined by grab sampling. The external exposure was

evaluated by thermoluminescent dosimetry. For dose calculations, the pathways

taken into account were external exposure and internal exposure, from water con-

sumption and air inhalation. The results obtained in this study show that the min-

ing activities do not imply in any detectable increment to the radiation doses to

which individual members of the general public are exposed.

Page 132 of 199


RADIONUCLIDES IN SWEDISH DRINKINGWATER

Britt-Marie Ek

Geological Survey of Sweden, POBox 670, S- 751 28 Uppsala, SWEDEN


Directives from the European Union state that drinking water should be consumed

without risk. For radon and other radionuclides in drinking water there are guide-

lines and recommendations. The EU preparatory working group 1 ”Chemical pa-

rameters” suggest that a toxicologically based standard should be introduced for

uranium. The WHO suggests a guideline value for uranium based on its chemical

toxicity to 9 µg/l.

In accordance with the European union the Swedish health authorities have decid-

ed on new regulations for drinking water from the 25 of December 2003. The reg-

ulations state that the effective dose from radioactivity in drinking water should not

exceed 0.1 mSv/year. In this neither tritium, potassium 40K nor radon and its

daughters are included.

The natural radioactivity of Swedish drinking water is high in an international com-

parison. The reason for this is that the Precambrian bedrock of Sweden, especial-

ly granites, are rich in uranium and thorium. Wells drilled in the bedrock can have

high concentrations of radionuclides while dug wells generally have very low con-

centrations.

Page 133 of 199


Central and local authorities have recommended and urged people to analyze

radon in their drinking water during the past decades. It is calculated that approxi-

mately 35 000 analyses of radon in drilled wells have been performed. From the

results it is calculated that 10 000–15 000 out of 200 000 drilled wells in Sweden

have radon levels above 1 000 Bq/l.

Analyses of the other radionuclides in drinking water are as yet few. Analyses of

radium in 499 drilled wells 1988 showed that radium rarely occur in high concen-

trations. A former study of uranium in drinking water from 269 drilled wells in Upp-

sala county gave a mean of 21.1 µg/l and a median value of 12 µg/l.

This study will present results from analyses of radionuclides in drinking water

from selected areas of Sweden. In 103 drilled wells was the median content of

uranium 238U 7.3 µg/l, for radium 226Ra the median content was 0.02 Bq/l and for

radon the median content was 360 Bq/l. The median value for gross alpha was

0.66 Bq/l and för gross beta 0.3 Bq/l. The correlation between the radionuclides

were very weak.

Page 134 of 199


RELEASE OF NORM-RESIDUES FROMSURVEILLANCE IN GERMANY – SOME

PRACTICAL EXPERIENCE

Rainer Gellermann

HGN Hydrogeologie GmbH, Waller Weg 22, D-38112 Braunschweig, GERMANY

phone: ++49 531 23170300


In Annex XII Part A of the German Radiation Protection Ordinance (StrlSchV) ra-

dioactive residues resulting from work activities are specified. If their specific activ-

ity is higher than a surveillance threshold (Überwachungsgrenze) they have to

kept under surveillance. The disposal of such residues needs an official notifica-

tion of clearance. The procedure for obtaining such a notification of clearance re-

quires to file an application by the owner of the residues with the following content:

- declaration of the residues (type, mass, specific activity),

- statement of the disposal company regarding the acceptance of radioactive

residues,

- evidence of conformity with the waste law,

- proof that the dose limit of 1 mSv/year to the individual will be kept.

In order to simplify the preparation of the application a well structured document

containing all necessary statements and proofs was developed by us. It consists

of 6 application formulars and 2 or 3 reports. It enables an effective preparation of

Page 135 of 199


the application form and a speedy examination of the proposal by the authority.

However, the first experience obtained show several open problems to be solved

in future.These will be presented and discussed in the paper.

Page 136 of 199


IDENTIFICATION OF ENHANCEDCONCENTRATIONS OF 210PB AND 210PO IN

DUST SAMPLES FROM STEEL-WORKS

J. Döring1), J. Gerler1), M. Beyermann1), U.K. Schkade1), J. Freese2)

1) Federal Office for Radiation Protection, D-10318 Berlin, GERMANY2) Arcelor Group, D-15872 Eisenhüttenstadt, GERMANY

A study has been initiated to investigate the naturally occurring radioactivity in

byproducts of the industrial iron-ore reduction process such as sinter-dust and

blast-furnace dust. In a first step, dust samples obtained from the air stream

cleaning procedure at one production place have been investigated. Enhanced

concentrations of 210Pb and 210Po radionuclides have been found through mea-

surements of the emitted gamma and alpha radiations.

Thus, these materials have to be handled according to the regulations outlined in

the German Radiation Protection Ordinance, Part 3, Appendix XII, i.e., recycling or

disposal of these materials are controlled by law. In the presentation, the mea-

surements performed, the results as well as the specific regulations which have to

be applied to these materials will be given.

Page 137 of 199


TEST OF THE MATERIAL FOR RADON SEALLAYER AT THE MINE WASTE DISPOSAL SITE

JAZBEC

Jozef Rojc, Mine Zirovski Vrh

Peter Jovanovic, Institute of Occupational Safety, SLOVENIA

About 1.4 million ton of the mine waste material was deposited at the mine waste

disposal site Jazbec during the uranium ore mining in the uranium mine Zirovski

Vrh. The average concentration of uranium in the mine waste is about 60 g/ton,

the average specific activity of Radium 226Ra is 730 Bq/m3. To reduce the radon

exhalation rate and to reduce the penetration of the rainfall water into the waste

pile it should be covered with an appropriate material.

The surface of the waste pile is about 5 ha. The thickness of the cover should be

about 2 m.

A test field on the waste pile Jazbec (100 m long and 12–20 m wide) was con-

structed in the year 2003. The surface of the test field was separated in two parts:

one part with multi layer cover (5 layers), the second part with only two layers. For

the seal layer the fine clayey silt and sand was used. The measurements of radon

exhalation were done on the mine waste material, on the seal layer, on the protec-

tion layer and finally on the humus layer. For radon exhalation measurements a

method with charcoal absorbers was applied. The time of exposure was 48 hours.

The results of radon exhalation rates assure that clayey silt and sand mixture is

adequate material to use for radon barrage. The average results of radon exhala-

Page 138 of 199


tion rates are 50% and more percent lover than obligatory authorized limit of 0.1

Bq/m2s. The results of the water penetration measurements are not as low as it is

required by regulations. The improvement of clayey silt and sand characteristics

with bentonite was also evaluated.

Page 139 of 199


ESTIMATION OF RADON DOSE IN SEVERALWORKPLACES USING DOSIMETRIC MODEL

FOR INHALATION OF AIRBORNERADIONUCLIDES

Kalina Mamont-Cieśla, Olga Stawarz


POLAND

There are two approaches to the estimation of the effective dose associated with

the inhalation of 222Rn short-lived progeny. One of them based on the Publication

65 ICRP (International Commission on Radiological Protection ) using a single

dose conversion factor, called conversion convention, is derived from the results

of the epidemiological studies of uranium miners. However, the extrapolation from

the lung cancer risk for uranium miners applied to the general population meets

many objections related to both: big difference of about 2-3 orders of magnitude in

the radon exposure, and differences in the exposure environments (e.g. concen-

tration, size distribution and chemical composition of aerosols), breathing rates,

smoking pattern and so on. The second approach is based on the Publication 66

ICRP which strongly recommends the usage of dosimetric models for inhalation of

airborne radionuclides. These models reveal that the dose per unit intake of radon

progeny depends on the site of particle deposition in the respiratory track, which,

in turn, strongly depends on the particle size distribution. It is particularly important

Page 140 of 199


in the estimation of the dose to take into account the contribution of the ultrafine

particles below10 nm in diameter. To recapitulate, for the reliable estimation of the

radon dose it is necessary to know not only the alpha potential energy concentra-

tion (PAEC), but also the full size distribution of radon progeny particles in the

range from 1 to 1000 nm, which penetrate to our lungs with the air. The dosimetric

model approach uses a weighted dose conversion factor, which combines radon

progeny size distribution with the particle-size dependent dose conversion factors

in a particular exposure location.

By means of our Radon Progeny Particle Size Spectrometer, manufactured by dr

Stephen Solomon in ARPANSA, Melbourne, Australia, we measured potential al-

pha energy concentration (PAEC) and radon progeny size distribution in five work-

places. They were: an attorney office, Faculty of Physics at the Warsaw University

– two locations, the Central Laboratory for Radiological Protection and an experi-

mental coal mine “Barbara”. The measurements were conducted in various condi-

tions of aerosols: natural and high level aerosols from smoking cigarettes. We ap-

plied both approaches for the estimation of the annual effective doses from in-

haled radon progeny for an adult male with a breathing rates of 1.2 m3/h and 0.78

m3/h, appropriate respectively to occupational and environmental exposure, and

compared them. Ratios of the doses estimated by the dosimetric model to ones

with the use of the constant conversion convention range from 0.5 when the free

fraction is ca. 5% to 1.7 when the free fraction is ca. 30%.

Page 141 of 199


SAMPLE CLEAN-UP BY ON-LINECHROMATOGRAPHY FOR THE

DETERMINATION OF PU AND AM INSEDIMENTS

Jussi Jernström, Maria Betti

European Commission, Joint Research Centre, Institute for Transuranium

Elements, P.O.Box 2340, 76125 Karlsruhe, GERMANY


Plutonium is the most investigated actinide element in samples of different matri-

ces. A complete inventory of its isotopic composition can be obtained by different

analytical techniques i.e. mass spectrometry for the determination of 239Pu/240Pu

isotopic ratio, alpha spectrometry for the 238Pu and 239(40)Pu determination, and liq-

uid scintillation counting for the determination of 241Pu. To obtain good results,

separation of Pu from the matrix as well as other actinide elements is necessary.

In this paper a novel clean-up procedure for the determination of Pu and, conse-

quently, Am in environmental samples analysed by alpha spectrometry is present-

ed. The method is based on the purification of the samples from different standard

matrices (sediments etc.) and separation of Pu and Am by using three different

chromatographic columns and two different eluents. The eluted fractions are col-

lected at different times, and are checked for pureness by alpha spectrometry.

Page 142 of 199


This procedure, discussed in terms of analytical figures of merit, has been validat-

ed with certified reference materials and compared with the classical routine meth-

ods for alpha source preparation.

Page 143 of 199


THE INVENTORY OF ITALIAN NORMCONCERNED WORK ACTIVITIES IN THEFRAME OF ENVIRONMENT PROTECTION

F. Trotti1), C. Zampieri1), S. Bucci2), G. Clauser3), G. Colombo4), D.Desideri5), M. Facchinelli3), L. Gaidolfi6), G. Torri7)

1) ARPA Veneto – Regional Agency for the Environmental Protection of

Veneto via A. Dominutti 8, 37135 Verona, ITALY

e-mail: [email protected] ; [email protected]

2) ARPA Toscana – Regional Agency for the Environmental Protection of

Toscana, via Ponte alle Mosse 211, 50144 Firenze, ITALY, e-mail:

[email protected]

3) APPA Trento – Provincial Agency for the Environmental Protection of

Trento, Piazza A. Vittoria 5, 38100 Trento, ITALY4) ENI S.p.A. Divisione Exploration & Production, via Emilia 1, S. Donato

Milanese (MI), ITALY


5) Institute of General Chemistry – Urbino University, Piazza Rinascimento 6,

61029 Urbino, ITALY6) ARPA Emilia Romagna – Regional Agency for the Environmental Protection

of Emilia Romagna, via XXI Aprile 48, 29100 Piacenza, ITALY

Page 144 of 199


7) APAT – Agency for the Environmental Protection and for Technical

Services, via V. Brancati 48, 00144 Roma, ITALY

The importance of NORM in Italy, from the radiation exposure point of view both

for workers and for the public, is confirmed by a national decree (n. 241/2000), im-

plementing the EU BSS, that provides the execution of controls for a set of work

activities.

A project aimed at estimating environmental impact for some activities dealing

with NORM is being carried out by the National Topic Centre on Physical Agents

(CTN-AGF), coordination of Regional Environmental Protection Agencies (ARPA),

which supports the National Environmental Protection Agency (APAT) in collecting

environmental information about physical pollutants (ionizing and non-ionizing ra-

diations, noise). By now the following working categories have been chosen: phos-

phate and fertilizers industry, integrated steelworks, processing of zircon sands, oil

and gas extraction, uranium mines, coal-fired power plants.

Information about presence and features of different working cycles has been ob-

tained through field reports, representatives of sector associations or of the com-

panies themselves.

Radiological surveys have been carried out to increase knowledge for some work

activities aspects potentially relevant as far as environmental impact is concerned

(on dusts and residues in refractory, tiles industry and in integrated steelworks

etc.)

Technical data related to the various work activities have been collected by means

of specific questionnaires sent to most of the involved factories: a centralized data

base has been set up. An estimate of Italian work activities general environmental

pressure, first step for radiological impact predictions, is possible based on both

radiological information (present and already available) and technical information

from the questionnaires.

Page 145 of 199


URANIUM ISOTOPES IN PUBLIC DRINKINGWATER IN POLAND

Zofia Pietrzak-Flis, Iwona Kamińska, Edward Chrzanowski


POLAND


238U, 234U and 235U were determined in tap water samples collected from water sup-

ply systems located in various parts of Poland. The systems were supplied with

water from rivers or lakes (surface water) and from underground wells (under-

ground water).

Uranium isotopes were determined in 5-L samples. 232U was used as an internal

tracer. After water evaporation, uranium was chemically separated by anion ex-

change and extraction. Finally uranium was electrodeposited on a stainless steel

disc and activity of uranium isotopes was measured by alpha spectrometry.

Average activity concentrations of 238U, 234U and 235U in tap waters originating from

surface waters were 10.3±1.96 mBq L-1, 13.8±2.68 mBq L-1 and 0.44±0.08 mBq

L-1, respectively. Average activity concentrations of these isotopes in tap water

originating from underground waters for 238Uand 234U they were 4.53±1.50 mBq L-1

and 5.68±1.72 mBq L-1, respectively, whereas for 235U in six out of 16 water pipes

the concentrations were below the lower limit of detection (0.06 mBq L-1), and for

the other the average was 0.29±0.09 mBq L-1.

Page 146 of 199


Activity concentrations of 234U were higher than those of 238U (atomic 234U/238U ra-

tios ranged from 1.07 to 2.6), indicating the lack of equilibrium between these iso-

topes. The 234U/238U ratios for the surface and underground waters were similar.

The average activity ratio of 235U to 238U for water samples was equal to

0.045±0.003 which is close to the value 0.046 for uranium in nature.

In seven water supply systems the samples were taken before and after water

treatment. Only in one water source the treatment reduced the uranium content

significantly (by about a half), while in the other sources the treatment usually did

not decrease the uranium content. The activity concentrations of uranium isotopes

in tap waters taken from surface waters were similar to those from rivers and lakes

in Poland [1].

Reference

[1] Z. Pietrzak-Flis, I. Kamińska, E. Chrzanowski, Uranium isotopes in waters and

bottom sediments of rivers and lakes in Poland, prepared for publication.

Page 147 of 199


CHARACTERISATION OF SCALE FROM AFORMER PHOSPHORIC ACID PROCESSING

PLANT

Helen Beddow1), Stuart Black1), David Read2)

1) Environmental Radioactivity Research Group, School of Human &

Environmental Sciences, Whiteknights, PO Box 227, University of Reading,

Reading RG6 6AB, UNITED KINGDOM


2) Enterpris Ltd., Whiteknights, University of Reading, Reading RG6 6AB,

UNITED KINGDOM

A wide variety of industries extract and/or process ores and minerals containing

naturally occurring radioactive material (NORM). In many cases the industrial pro-

cessing of natural feedstock results in radioactive material becoming concentrated

in (by-) products, wastes and plant installations. The main sources of NORM are

members of the 238U and 232Th decay chains. The radioelements of greatest con-

cern are radium, lead and polonium, due to their radiological and toxicological

properties when inhaled and/or ingested (Kathren, 1998). Therefore, it is neces-

sary for radioactive materials to be isolated from the human environment, thereby

committing industries to costly disposal initiatives under the current directives.

Scale samples were collected from a phosphoric acid processing plant, which is

currently in the process of being demolished. These materials were analysed

Page 148 of 199


chemically, mineralogically and radioactively to determine the nature and concen-

tration of the radionuclides retained in pipe work and process plant (Poole et al.,

1995). Three areas of the site were investigated; 1) the Green Acid Plant, where

crude acid was concentrated; 2) the green acid storage tanks; and 3) the Purified

White Acid (PWA) plant, where inorganic impurities were removed. The scale

samples predominantly comprised: fluorides (e.g. malladrite, iron oxide fluoride);

calcium sulphate (e.g. bassanite); and an assemblage of fluorides and phos-

phates (e.g. iron fluoride hydrate, calcium phosphate) respectively, which can be

related to the process occurring at each of these locations. The radioactive inven-

tory is primarily all from 238U and its decay chain products. Compared to the feed-

stock ore values, elevated concentrations, to levels ≤8.8 Bq/g of 238U, and its

daughter 234Pa, were found to be retained in installations where the process

stream was rich in fluorides and phosphates. Enriched levels, ≤ 11 Bq/g of 226Ra

were found in association with precipitates of calcium sulphate. Fractionation of226Ra from its daughter 210Pb was observed in some scales; however, 210Pb levels

in excess of its parent was also noted in many materials from the PWA plant,

which may be attributed to the purification process occurring in this installation. In

addition, enriched concentrations of trace elements Pb (≤106), Cu (≤152 ppm), Ni

(≤215 ppm), Zn (≤2183) and particularly Cr (≤3110 ppm) were also found in many

of the materials analysed.

Reference:

Kathren R. L. (1998) NORM Sources and Their Origins. Applied Radiation and

Isotopes 49(3), 149-168.

Poole A.J., Allington D.J., Baxter A.J., and Young A.K. (1995) The natural radioac-

tivity of phosphate ore and associated waste products discharged into the eastern

Irish Sea from a phosphoric acid production plant. The Science of the Total Envi-

ronment 173/174, 137-149.

Page 149 of 199


VENTILATION: A TECHNIQUE FOR INDOORRADON MITIGATION

K. Kant1), R.P. Chauhan2), S.K. Chakarvarti3)

1) Department of Physics, KLMDN College for Women, Faridabad, Haryana,

INDIA – 1210012) Department of Physics, I.G.N.College, Ladwa, Kurukshetra (Haryana),

INDIA – 136 1323) Department of Applied Physics, NIT, Kurukshetra (Haryana), INDIA –

136119

The problem of radon is an important global problem of radiation hygiene concern-

ing the world population. It has been estimated that the radon, largely in homes,

constitutes more than 50% of the dose equivalent received by general population

from all sources of radiation, both naturally occurring and man-made. When radon

decays to form its progeny (218Po and 214Po), they are electrically charged and can

attach themselves to tiny dust particles, water vapours, oxygen, trace gases in in-

door air and other solid surfaces. These daughter products remain air borne for a

long time. These dust particles (aerosols) can easily be inhaled into the lung and

can adhere to the epithelial lining of the lung, thereby irradiating the tissue. As per

the ICRP recommendations, it is essential to adopt remedial measures if the

radon levels in dwellings are found to be more than 200 Bq m-3. Ventilation pro-

cess can simulate the conditions generated through advection or diffusion and can

be effective in mitigating indoor radon.

Page 150 of 199


In the present work, the effect of ventilation (natural and forced by exhaust fan

used at different speeds), on radon concentration in a room having an external

source of radon was studied. For radon, the LR-115, type II solid state nuclear

track detectors (SSNTDs) were used. The radon reduction factor, which is the ra-

tio of radon concentrations before and after remediation was calculated. The

radon reduction factor was found to vary from 1.08 to 1.17 due to natural ventila-

tion whereas 1.17 to 3.01 due to forced ventilation. The results indicate that opti-

mized ventilation (natural or forced) can be a simple mean to mitigate radon in

dwellings.

Key words: Radon concentration, remediation, ventilation, SSNTDs, exhaust fan

Corresponding author: E-mail: [email protected], Phone: 91-129-2461602

Page 151 of 199


IN SITU GAMMA-RAY SPECTROMETRY INCOMMON ROCK RAW MATERIALS

MINED IN KRAKOW VICINITY, POLAND

D. Malczewski, L. Teper, G.Lizurek

Faculty of Earth Sciences, University of Silesia; Będzinska 60, 41-200 Sosnowiec,

Poland; Tel.: +48(032) 3689370; Fax: +48(032)2915865


J. Dorda

Institute of Physics, University of Silesia; Uniwersytecka 4, 40-007 Katowice,

Poland;

The natural radioactivity of 40K, 208Tl, 212Pb, 212Bi, 214Pb, 214Bi, 228Ac and the fallout of137Cs in common rock raw materials mined in Krakow vicinity were measured in

situ using a portable gamma-ray spectrometry workstation. The measurement

points were chosen for different regional rocks in: Devonian and Jurassic lime-

stones, dolomite, trachyandesite, porphyry, porphyry tuff, diabase and melaphyre.40K activity varied in the range from about 82 Bqkg-1 (Jurassic limestone) to 3150

Bqkg-1 (porphyry tuff). The activity concentrations associated with 228Ac (232Th se-

ries) varied in the range from 9 Bqkg-1 (Jurassic limestone) to 56 Bqkg-1 (porphyry

tuff), whereas activity of 226Ra (238U series) ranged from about 13 Bqkg-1 (Jurassic

limestone) to 43 Bqkg-1 (Devonian limestone). The highest deposition of 137Cs (20

Page 152 of 199


kBqm-2) was recorded in Devonian limestone. Since many of these rocks are used

as building materials, evaluation of radioactive elements concentrations in these

materials is important because indoor radiation exposure can vary depending on

used building materials.

Page 153 of 199


SOURCES OF TENORM – INVENTORY OFPHOSPHATE FERTILIZERS AND ALUMINUM

INDUSTRIES

Dan Georgescu, Florian Aurelian, Mihai Popescu, Cornel Răd-ulescu

Research & Development National Institute for Metals and Radioactive Resources

Romania, Bucharest, ROMANIA


I. Phosphate fertilizers industry

In Romania, there were built and commissioned in the period 1964–1978, 7 fertili-

zers plants based on H2SO4 and HNO3 attack.

A H2SO4 attack

The deposit with sub-products (phosphogypsum) from SC SOFRET SA Bacau.

The material (phosphogypsum) resulted from H2SO4 attack of the imported pho-

sphatic rocks has been deposited since 1978, close to the plant, which is located

in the Eastern part of Bacau city. In the samples resulted from the surface of the

phosphogypsum deposit and also from drills until a depth of 16 m there were

detected the following contents in radioelements: U = 15–21 ppm, 226Ra = 0.45–

0.87 Bq/g, Th = <3 ppm, K = <1%, gamma dose flow rate between

0.18–0.25 μSv/h. Radon concentration at the pond surface (irregular areas) was

of 4860 Bq/m3 and for thoron was of 496 Bq/m3.

Page 154 of 199


B HNO3 attack

The tailing pond with sub-products from S.C. AZOMURES S.A. Targu-Mures. The

tailing pond with technological water and calcium carbonate occupies a surface of

about 33 ha, close to the plant, which is located in the Western part of Targu-

Mures city. The technological water from the tailing pond has a pH = 1.45 and the

contents in U = 0.045 mg/l and

Ra = 1.4 Bq/l. The sub-product (calcium carbonate) contains 23 ppm U, 0.35 Bq/g

Ra, 2 ppm Th and 0.2% K.

II. Aluminum industry

A. Alumina Plant from Oradea

In the western area of Oradea city there is the bauxite processing plant. In the

pond with red sludge resulted from alumina acquirement, the contents in radionuc-

lides are mentioned below (Table 1):

Table 1ppm

U

Bq/g

Ra

ppm

ThMaterial of red colour 11 0,21 61Material of dark colour <10 0,137 70Material of light colour 127 1,675 11

In air at the pond surface: 222Rn = 21 Bq/m3, thoron = 1220 Bq/m3. In water from

the red sludge pond: 222Rn = 101 pCi/l, thoron = 0, 226Ra = 0.023 Bq/l, pH = 12.05.

B. Alumina Plant from Tulcea

Sub-product – red sludge: U = 15 ppm; 226Ra = 0.212 Bq/g; Th = 62 ppm. In water

from pond: pH = 12.2; 226Ra = 0.026 Bq/l; U = 0.010 mg/l. 222Rn and thoron distri-

bution in air at the red sludge pond surface: 222Rn = 248 Bq/m3, thoron = 6270

Bq/m3.

Page 155 of 199


RADON MEASUREMENTS AS A MONITORINGPOSSIBILITY FOR MINING SUBSIDENCE

OCCURRENCES

A. Kies1), A. Storoni2), Z. Tosheva1)

1) Laboratoire Physique des Radiations, Université du Luxembourg, 162A

avenue de la Faïencerie, L-1511 LUXEMBOURG


2) Cellule de Recherche en Géographie Physique, 162A avenue de la

Faïencerie, L-1511 LUXEMBOURG

The objective of the current research is to check whether or not radon concentra-

tions in the surface layer can be related to mining and mining subsidence voids in

order to allow the drawing of a subsidence risk map.

The chosen test site is located in a forested area on the plateau of the Luxem-

bourg mining basin. Under an overburden of 65 m thick limestone and marls two

approximately 3-m-high iron layers have been worked between 1920 and 1950.

Due to the prevailing room-and-pillar extraction method, pillars of different shape

and size have been kept in place. Mining subsidence has progressively occurred

for more than 50 years and is currently going on. Along the western mine bounda-

ry a long surface fissure has developed and some 25 subsidence pits occurred

over a period of several decades, the last in 1995. The site was mainly chosen be-

cause it has a more or less uniform surface, the old mining maps still exist and fur-

Page 156 of 199


ther subsidence may be expected the more than the neighbouring busy road has

not been protected by a continuous pillar.

The ease of radon to leave the site of production in the soil and rocks and the dif-

ferences in the subsequent possibility to migrate and concentrate in underground

voids, give the possibility to locate underground inhomogeneities by a survey ba-

sed on radon soil measurements. Normally mining voids situated at a depth of 60

m have no influence on radon concentrations measured in one meter depth. But

due to mining subsidence, an important brittleness of the rocks can develop

moving up to the surface; as a consequence we expect locally increased radon

concentrations. We report of an intensive investigation on radon in soil measure-

ments, distributed over 10 parallel transects. Along a transect the spacing

between the measurement points was 4 meter, for 8 transects the inter-distance

was 10 m, it was 30 m for the last two transects.

Radon concentrations plotted against sample spacing are very irregular docu-

menting a very inhomogenious subsoil. The map of the radon concentrations

(Fig.1) shows these irregularities, bur on the whole it is possible to identify a trend

from East to West, corresponding to the main directions of the old mine roadways.

The location of enhanced radon concentrations may present an increased subsi-

dence risk consecutive to a fractioning of the underground. This study documents

that investigations based on radon in soil can contribute to risk investigation rela-

ted to mining subsidence occurrences.

0

10

20

30

40

50

60

70

80

90

Fig. 1: Map of radon concentrations (in Bq/m3)

Page 157 of 199


NATURALLY OCCURING RADIOACTIVEMATERIAL (NORM) ASSESSMENT OF OIL

AND GAS PRODUCTION INSTALLATIONS INNIGERIA

S.B. Elegba1), I.I. Funtua2)

1) Nigerian Nuclear Regulatory Authority (NNRA), Abuja, NIGERIA2) Centre for Energy Research and Training, Ahmadu Bello University, Zaria,

NIGERIA,


Naturally Occurring Radioactive Material (NORM) assessment was carried out at

oil production platforms and gas processing units in Nigeria with the aim of establi-

shing baseline levels and problem areas. The assessment consisted of external

radiation measurements on production units, from the wellheads to the product

outlets, sampling and gamma spectrometric analysis of scales and sludge from

pig stations and of replaced pipes and vessels. The NORM levels on the installa-

tions and associated equipment ranged from 0.1 to 15 Sv/h and spectrometric

analysis indicate the presence of 226Ra, 214Bi and 214Pb in the scales and sludge

having maximum concentration of 200 Bq/g. The levels may seem low but there is

still the need to establish routine monitoring program for the Industry, which

presently is non-existent.

Page 158 of 199


Page 159 of 199


NATURALLY OCCURRING RADIONUCLIDESIN RAW MATERIALS, PRODUCTS AND

WASTEIN THE STEEL INDUSTRY

Hanna Firganek, Artur Żak, Jarosław Marcisz

Institute for Ferrous Metallurgy, K. Miarki 12, 44-100 Gliwice, POLAND,


The Institute for Ferrous Metallurgy (IFM) activities in the field of the monitoring of

the radioactive contamination in the steel industry are presented. The research

was carried out in the framework of EUREKA “Intracem” project.

The aim of the activities is development of integrated radiation protection system

for Polish steel industry (comprising staff, products, waste and environment).

Definition of “steel industry” includes also other cooperating manufactures and

companies i.e.: suppliers or producers of scrap, raw materials and refractory

products.

The scope of interest includes both artificially and naturally occurring conta-

minating radionuclides (NORM).

Page 160 of 199


CHARACTERISATION OF SCALE FROM AFORMER PHOSPHORIC ACID PROCESSING

PLANTCOMPLETE LECTURE TEXT

Helen Beddow1), Stuart Black1), David Read2)

1) Environmental Radioactivity Research Group, School of Human &

Environmental Sciences, Whiteknights, PO Box 227, University of Reading,

Reading RG6 6AB, UNITED KINGDOM


2) Enterpris Ltd., Whiteknights, University of Reading, Reading RG6 6AB,

UNITED KINGDOM

A wide variety of industries extract and/or process ores and minerals containing

naturally occurring radioactive material (NORM). In many cases the industrial pro-

cessing of natural feedstock results in radioactive material becoming concentrated

in (by-) products, wastes and plant installations. The main sources of NORM are

members of the 238U and 232Th decay chains. The radioelements of greatest con-

cern are radium, lead and polonium, due to their radiological and toxicological

properties when inhaled and/or ingested (Kathren, 1998). Therefore, it is neces-

sary for radioactive materials to be isolated from the human environment, thereby

committing industries to costly disposal initiatives under the current directives.

Scale samples were collected from a phosphoric acid processing plant, which is

currently in the process of being demolished. These materials were analysed

Page 148 of 199


the bed refractory masses). There were carried out the analysis of the possibility

of the implementation of contaminated mould fluxes as a tracers of the surface

non-metallic inclusions in steels.

Page 162 of 199


ANALYTICAL METHODS USED FORDETERMINING NATURAL RADIONUCLIDES

IN FINNISH DRINKING WATER

Pia Vesterbacka, Laina Salonen

Radiation and Nuclear Safety Authority, Laippatie 4, 00880 Helsinki, FINLAND


Natural radioactivity in Finnish drinking water sources comes mainly from decay

series of 238U. Radon (222Rn) has the greatest contribution to the radiation dose.

The long-lived alpha-active isotopes of uranium (238U and 234U), polonium (210Po)

and radium (226Ra) and beta-active lead (210Pb) and radium (228Ra from 232Th

series) isotopes cause high doses very rarely. For most of Finns, the radiation

dose caused by natural radionuclides in drinking water is low. Only those people,

who consume water from drilled wells, may obtain high doses via drinking water.

During the last 35 years STUK has studied radioactivity in drinking water that origi-

nate either from surface or ground water sources. Now more than 1.000 water-

works, 8.000 wells drilled in bedrock and 5.000 wells dug in soil have been

studied. The present database includes results from 50.000 measurements or

analyses.222Rn is measured with a liquid scintillation spectrometer in a homogeneous

solution. Most samples coming for radon measurement are screened by gross al-

pha and beta measurements in order to find the occurrence of 238U, 234U, 226Ra,

Page 163 of 199


210Po, 40K, 210Pb and 228Ra in water. Uranium (238U, 234U) and 226Ra contents can be

calculated from gross alpha spectrum fairly accurately for most of the samples.

Nuclide specific analysis with radiochemical methods are carried out if more preci-

se information of 234U, 235U, 238U, 210Po or 210Pb contents are required.

Measurements are nowadays carried out with the liquid scintillation spectrome-

ters, Quantulus 1220TM (for gross alpha and beta, 210Pb) and Guardian 1414TM

(for radon and gross alpha) and with the alpha spectrometer, AlphaAnalystTM (for

uranium and 210Pb–210Po).

Page 164 of 199


RADIUM LEACHING FROM MINE DEPOSITSAS A POSSIBLE SOURCE

OF GROUNDWATER CONTAMINATION

Stanisław Chałupnik

Laboratory of Radiometry, Central Mining Institute 40-166 Katowice, Pl. Gwarków

1, POLAND


Saline waters occurring in underground coal mines in Poland often contain natural

radioactive isotopes, mainly 226Ra from uranium series and 228Ra from thorium

series. Approximately 40% of total amount of radium remains underground in a

form of radioactive deposits, but 225 MBq of 226Ra and 400 MBq of 228Ra are re-

leased daily to the rivers with mine effluents through surface settling ponds. Very

peculiar situation is observed in coal mines, where as a result of precipitation of

radium from radium-bearing waters radioactive deposits are formed. Sometimes

natural radioactivity of such materials is very high, in case of scaling from coal

mines radium concentration may reach 400 000 Bq/kg – similar activity as for 3%

uranium ore. Usually such deposits can be found underground, but sometimes co-

precipitation of radium and barium takes place on the surface, in settling pond and

in rivers. Therefore maintenance of solid and liquid waste with technologically en-

hanced natural radioactivity (TENORM) is a very important subject.

Page 165 of 199


Lately another problem appeared – due to the decrease of the production of Po-

lish coal industry and dismantling of several coal mines, also the ground recla-

mation should be done in their vicinity. But in several cases deposits in the ponds

contain enhanced levels of radium concentration. Therefore laboratory tests were

done to investigate a possibility of the re-entry of radium into groundwater or river

waters from such deposits. Results show, that in case of insoluble barium and ra-

dium sulphates co-precipitated out from waters type A, re-entry ratio is very small.

Different situation can be observed in case of radium, adsorbed on bottom sedi-

ments from waters type B, because re-entry ratio is much higher. Nevertheless,

this phenomenon seems to be not so important and significant for the further pol-

lution of the adjacent areas of the settling ponds in the future.

Page 166 of 199


MEASUREMENT OF SHORT-LIVED RADONDAUGHTERS IN POLISH MINES

Krystian Skubacz, Antoni Mielnikow

Laboratory of Radiometry, Central Mining Institute, 40-166 Katowice, Pl. Gwarkow

1, POLAND


Obligatory measurements of the potential alpha energy concentration of short-li-

ved radon daughters have been performing in the Polish underground mines since

1989 year. In consideration of economical aspects, it is attempted from the very

beginning to combine it with measurements of the dust concentration. Therefore

the developed measuring units were an integral part of the dust samplers com-

plying the requirements of the State Mining Authority to apply it in underground

mines. This way the developed devices could fulfil two measurement tasks simul-

taneously: measurement of the dust concentration and potential alpha energy

concentration of short-lived radon daughters. The new device based on the ther-

moluminescence detectors is able to co-operate with the SKC universal pumps

equipped with a cyclone making it possible to operate constantly for a one working

day. The lover limit of detection was equal about 0.04 J/m3 at a 95% confidence

level and 1-hour pumping.

Page 167 of 199


RADIUM REMOVAL FROM MINE WATERS –UNDERGROUND TREATMENT

INSTALLATION

Małgorzata Wysocka, Stanisław Chałupnik, Elżbieta Molenda

Laboratory of Radiometry, Central Mining Institute, 40-166 Katowice, Pl. Gwarków

1, POLAND


In underground coal mines in the Upper Silesian Coal Basin there are inflows of

highly mineralised waters containing radium isotopes. These waters cause ra-

dioactive pollution of the natural environment in mining areas. Therefore cleaning

of saline waters of radium is very important. Two types of radium-bearing waters

were distinguished – one type containing radium and barium ions, but no sulpha-

tes (type A) and another one in which radium and sulphate ions are present but no

barium (type B).

A very efficient and inexpensive method of purification of saline waters of Ba2+ and

Ra2+ ions was developed and implemented in two coal mines. As the result of

used technology, based on application of phosphogypsum as the cleaning agent,

a significant decrease of radium discharge was achieved – daily of about 120 MBq

of 226Ra and 80 MBq of 228Ra.

Another type of radium waters does not contain barium ions, but contains sulphate

ions 24SO . There is no carrier for co-precipitation of radium so radium is trans-

Page 168 of 199


ported with discharged waters to main rivers. Different method of purification from

radium must be applied for such waters. Laboratory and field experiments were

performed, and a cleaning method was chosen. For purification of saline waters –

waste products from other industrial processes are applied. The method of puri-

fication has been applied in full technical scale in coal mine with very good results

– of about 6 m3/min of radium-bearing waters is cleaned. Whole this process takes

place in underground old workings without any contact of mining crew with ra-

dioactive deposits, which are produced during the process. As a result radium

amount released to the natural environment was significantly diminished – ap-

proximately of about 90 MBq of 226Ra per day and 150 MBq of 228Ra.

Page 169 of 199


RADIUM BALANCE IN DISCHARGE WATERSFROM COAL MINESIN UPPER SILESIA

REGION

Stanisław Chałupnik, Małgorzata Wysocka, Antoni Mielnikow,Bogusław Michalik, Jan Skowronek


1, POLAND,


Saline waters from underground coal mines in Poland often contain natural ra-

dioactive isotopes, mainly 226Ra from the uranium decay series and 228Ra from the

thorium series. Approximately 60% of the total amount of radium remains under-

ground as radioactive deposits, but 120 MBq of 226Ra and 200 MBq of 228Ra are

released daily into the rivers along with the other mine effluents from all Polish

coal mines. Technical measures such as inducing the precipitation of radium in

gobs, decreasing the amount of meteoric inflow water into underground workings

etc., have been undertaken in several coal mines, and as a result of these measu-

res the total amount of radium released to the surface waters has diminished by

about 60% during the last 5–6 years.

Mine water can have a severe impact on the natural environment, mainly due to

its salinity. However associated high levels of radium concentration in river waters,

bottom sediments and vegetation have also been observed. Sometimes radium

Page 170 of 199


concentrations in rivers exceed 0.7 kBq/m3, which is the permitted level for waste

waters under Polish law. The extensive investigations described here were carried

out for all coal mines and on this basis the total radium balance in effluents has

been calculated. Measurements in the vicinity of mine settling ponds and in rivers

have given us an opportunity to study radium behaviour in river waters and to as-

sess the degree of contamination.

Page 171 of 199


THEORETICAL STUDY OF RADIUMBEHAVIOUR IN AQUIFERS

Stanisław Chałupnik


1, POLAND


In the paper, a theoretical approach to the problem of radium presence in minera-

lized mine water, is presented. Two main types of radium-bearing waters have

been found in Polish coal mines. In type A waters, radium isotopes are present

together with barium, while concentrations of sulphate ions are very low. Addi-

tionally, in these waters a ratio of 226Ra:228Ra activity is usually higher than 1. In

type B waters, no barium can be fund, but radium together with sulphate ions.

Contrary, in such waters the isotopic ratio of radium 226Ra:228Ra is below 1, and ac-

tivities of both isotopes of radium are lower as in type A waters. No other differen-

ces in chemical composition of mine waters have been observed.

Analysis shows, that the activity ratio of radium isotopes is related to the dynamics

of radium adsorption on the grains of solid phase in the aquifer. During analysis

must be taken into account, that the radium build up in formation water due to

recoil effect, is stable in time. Additionally, no correlation with elevated concentra-

tions of uranium and thorium in rocks, have been observed. Therefore the enhan-

ced radium content in formation waters must be caused by its mineralization.

Page 172 of 199


The relatively short half life of 228Ra (6 years) shows, that the process of radium

transfer from solid into liquid phase is a short term process for geological scale.

Therefore radium content in mine waters must be related to the concentration of

natural radionuclides in the close vicinity of the aquifer or the water reservoir.

Page 173 of 199


RADIUM BEHAVIOUR DURINGDESALINATION PROCESSES OF MINE

WATERS

Stanisław Chałupnik, Krystian Skubacz

Laboratory of Radiometry, Central Mining Institute

40-166 Katowice, Pl. Gwarków 1, POLAND


In 80’s and 90’s investigations of radium behaviour in desalination plant have

been performed by Laboratory of Radiometry of the Central Mining Institute. This

plant has been located in Dębieńsko Mine for complete removal of dissolved

solids from mineralized mine waters. The installation was a very unique solution,

the only one constructed for such purposes in Poland and all over the world. In the

plant brines from two coal mines have been treated. These salty waters were ad-

ditionally radium bearing ones, containing enhanced levels of radium isotopes

(226Ra and 228Ra). Our investigation showed enhanced concentrations of radium in

different waste materials and by-products of the process. Therefore the econo-

mical use of such products wasn’t possible.

In last years a plan of the construction of the desalination plant for another group

of mines was under the discussion (Piast and Ziemowit Collieries). Results of in-

vestigations of contamination of the natural environment, caused by radium-

bearing waters from these mines, indicated how severe this problem was. To

Page 174 of 199


solve this influence, the removal of radium in underground galleries has been ap-

plied in one of these mines.

On the basis of previous investigations in Dębieńsko Desalination Plant, an

analysis of radium behaviour in planned installation has been prepared. It was

done for two possible scenarios – without and with radium removal from mine wa-

ters, preceded the desalination process. Results of the analysis are presented in

the paper. This assessment gives a very good opportunity to point out how im-

portant may be radium removal from mine waters – not only to minimize environ-

mental pollution but also to enable utilization of certain products of desalination

process.

Page 175 of 199


INVESTIGATIONS OF SURFACE SETTLINGPOND

Małgorzata Wysocka, Stanisław Chałupnik

Laboratory of Radiometry, Central Mining Institute, 40-166 Katowice, Pl. Gwarków

1, POLAND


One of the problems, which may appear during ground reclamation of surface set-

tling ponds of underground mines, is enhanced radon exhalation from bottom

sediments. This problem would become more important, when concentration of

radium isotopes in sediments is enhanced due to discharge of radium-bearing wa-

ters into pond. For investigations, special radon accumulation chambers have

been designed and constructed. Concentration of radon in these chambers can be

measured with application of Lucas cells or activated charcoal detectors. In the

latter method radon is extracted from charcoal into liquid scintillator and such sam-

ple is measured in liquid scintillation spectrometer. Therefore the lower limit of

detection (LLD)

of the second metod is as low as 0.1 mBq/m2·s. while the LLD for Lucas cells is

only 1.5 mBq/m2·s.

Mentioned above methods of measurements of radon exhalation have been ap-

plied for investigations of surface settling pond of one Polish coal mines, abando-

ned and emptied at the beginning of year 2002. An agreement of the mine’s

management and the local authority is to make the ground reclamation of thePage 176 of 199


pond. A thick layer of sediments with enhanced concentration of radium isotopes

covers the pond’s bottom. Maximum concentration of radium isotopes in these

sediments is as high as 2.0 kBq/kg for 226Ra and respectively up to 4.0 kBq/kg in

case of 228Ra. Two years after the complete release of brines from the pond, bot-

tom sediments are still soaked with water. Therefore measurements of radon in

soil gas weren’t possible. On the other hand, in some parts of the pond investi-

gations of radon exhalation coefficient were done. Preliminary results of measure-

ments, done in 2002 year, showed that in specific sites of the pond, radon exhala-

tion rates were higher as the highest values of radon exhalation from the ground in

Upper Silesia region. Values of exhalation coefficient up to 200 mBq/m2·s have

been found. It must be pointed out, that preliminary measurements were done in

period, when water has been only partly removed from the pond and further dry-

up of sediments should lead to the increase of radon exhalation.

Data from the year 2003 confirm this assumption. During this period water content

in the bottom sediments has been significantly lower as previously and results of

measurements of radon exhalation were sometimes above 300 mBq/m2·s.

Vegetation transgression into the pond occurred during year 2003, mainly weeds.

Samples of vegetation have been collected from this area to measure radium

isotopes content and calculate transfer factors for radium isotopes. Very high con-

centrations of radium isotopes have been found at several sites. Another reason

of the pollution might be the leaching of radium from sediments and contamination

of groundwater.

Therefore mentioned above sources of radiation hazard must be taken into acco-

unt for planning and designing of reclamation operations for surface settling ponds

of underground mines.

Page 177 of 199


RADON IN SOME CAVES OF KRAKOW-CZESTOCHOWA JURASSIC UPLAND

Jan Skowronek, Małgorzata Wysocka, Michał Giebel


40-166 Katowice, Pl. Gwarkow 1, POLAND


Radon levels in caves and migration processes have been investigated worldwide

from many years. In Poland, contrary, there is no systematic measurements in

caves, except Lower Silesia region [3], although radon levels may reach several

kBq/m3 in particular caves – see tabel below.

Cave 222Rn (kBq/m3)Bear’s Cave (Poland) [3] 1.3Gyokusen-do (Japan) [3] 1.5Postojna Cave (Slovenia) [2] 2.3Mitchelstown Cave (Ireland) [1] 3.1Altamira (Spain) [3] 3.2

In the papers results of radon investigations in chosen caves of Kraków-

Częstochowa Upland are presented. Measurements have been performed during

summer of year 2003, from June to September. Different caves have been cho-

sen for our investigations – turistic ones with easy access, and caves with difficult

access, where specialistic speleological devices must be used. From geological

Page 178 of 199


point of view, caves located on the Upland were developed in karstic processes in

Upper Jurrasic limestones.

Maximum radon concentration has been found in Straszykowa Góra Cave – 7.3

kBq/m3, while lowest concentrations were measured in Zielona Góra Cave (near

Częstochowa) – 0.015 kBq/m3. A correlation between geological structure and ra-

don concentration in caves has been found. Usually higher radon concentrations

have been measured in caves, where tectonic deformations were negligible and

roof rocks weren’t weathered and fissured. An example of such type is mentioned

earlier Straszykowa Góra Cave, which walls and roofs are cemented by calcite, fil-

ling and insulating all fissures.

Opposite situation can be seen in caves, developed along huge fissured faults.

Examples of such caverns are Piętrowa Szczelina Cave, Mąciwody Cave,

Głęboka Cave or Zielona Góra Cave, where thickness of roof rocks is several me-

ters only, moreover these rocks are strongly weathered, therefore radon concen-

trations are low.

Till now, no correlation between radon levels and depth of particular caves has

been found. Very important problem is to pay special attention to caves with easy

access. In the Upland area 5 turistic caves are located and several others with

very easy access, but in no caves regular radon monitoring is done.

References

[1] Duffy J.T., Madden J.S., Mackin G.M., McGarry A.T. (1996). A reconnais-

sance survey of radon in show caves in Ireland. Environment International, 22,

415-423.

[2] Jovanovic P. (1996). Radon measurements in karst caves in Slovenia. Envi-

ronment International, 22, 429-432.

[3] Przylibski T. (1999). Radon concentration changes in the air of two caves in

Poland. Journal of Environmental Radioactivity, 45, 81-94.

Page 179 of 199


NORM LEGISLATION IN POLAND

Jan Skowronek




Polish Parlament (Seym) established November 29, 2000 year new Atomic law,

changing it significantly many regulations in compliance with EU law. Atomic Law

is in force since January 1, 2002 year.

In this act the regulations of peaceful appliance of the atomic energy, real and po-

tential risk due to the ionizing radiation from the artificial sources of radiation or

nueclear materials, nuclear wastes and used nuclear fuel. The regulations of the

nuclear safety, radioprotection of human and environment has been described in

this act, too.

In July 2001 year, Seym changed significantly Polish Geological and mining law.

This act is valid since January 1, 2002 year. In this act the regulations for the ra-

dioprotection of workers from natural sources of ionizing radiation were significan-

tly modified.

In this paper these new regulations are described with a special emphasis on the

lack of detailed regulations as regards of the mining wastes with enhanced natural

radioactivity.

Page 180 of 199


NORM IN MINING INDUSTRY IN POLAND

Jan Skowronek

Laboratory of Radiometry, Central Mining Institute,



The main branches of Polish mining industry are the coal, copper, zinc and lead,

salt and oil and gas mines. In many of these mines the problem of the naturally

occurred radioactive materials is present.

The main source of risk for the miners is due to the short-lived radon daughter

products present in air. This source of risk is present in all Polish underground

mines. In coal, copper and oil and gas mines the radium-bearing waters are

present. This is a potential risk for the miners, but for the environment too,

because all mine water is pumped out to the rivers. In coal and copper mines ra-

dium precipitates from the waters creating the risks of the internatal conata-

mination but of external gamma radiation too.

The Polish geological and mining law needs to perform monitoring of all sources

of natural radiation at the workplaces and to introduce the preventive measures, if

necessary. In this paper the results of the monitoring and prevention measures

are described.

Page 181 of 199


THE ASSESSMENT OF EXPOSURE TOIONIZING RADIATION AT SPOIL BANKS

Bogusław Michalik

Laboratory of Radiometry, Central Mining Institute,

40-166 Katowice, Plac Gwarków 1,POLAND


By the 1970 year Polish hard coal mining was not considered as source of ra-

diation exposure due to presence of enhanced concentration of natural radionucli-

des. After the radioactive scales in pipelines draining of brines had been found,

the necessity of radiation risk’s monitoring emerged. During few next years a lot of

different surveys have been carried out that resulted in the complex system of oc-

cupational radiological protection. In 1982 year due to relevant national rules the

system has been enforced into the whole of Polish underground mining. The sys-

tem consists of systematic measurements of particular factors of the miners’ ra-

diation risk, like radioactive aerosols, sediments and waters. Unfortunately, less

attention has been given to exposures that can occur as a result of releasing of

naturally radioactive materials to environment.

The territory the Upper Silesian Coal Basin is densely populated. Since the pheno-

menon of enhanced natural radioactivity has become well known to the members

of the public a lot of social troubles appear. Majority of them was unexpectedly

related to waste rocks piles that are deemed to be as danger as radioactive scales

Page 182 of 199


and sediments. According to claims of local societies the assessment of the ra-

diation exposure at waste rock piles has been done.

Concentrations of natural radionuclides in extracted from underground rocks sligh-

tly exceed the natural background on the Earth surface. This fact results in an en-

hanced gamma dose rate at the places where this kind of waste was dumped. Ad-

ditionally the structure of spoil banks creates possibility of radon exhalation’s in-

creasing. Taking into consideration the total amount of spoil and gangue and the

current international recommendation, the enhanced level of external radiation

and radon exhalation seems to be significant from point of view of radiological

science.

Due to the fact that the waste rock are not undergone any chemical transformation

the potential enhanced radiation risk is directly related to geological origin of rocks

that constitute that waste. Therefore for investigation two different mining regions

have been chosen. The coal seems, exploited in those regions, lie on different

carboniferous system so that properties of rocks occurring together with coal differ

each other. Measurements of radiation risk have been done on three waste rock

piles that vary in age and stage of land reclamation. For comparison the same

measurements have been done on neighbouring rural areas. The results of inve-

stigations shows that the major contribution to slightly enhanced radiation risk at

these areas derives from external irradiation due to enhanced concentration of na-

tural radioactivity in waste material.

Page 183 of 199


RANKING OF TENORMS IMPACT INTORADIATION RISK

Bogusław Michalik


40-166 Katowice, Pl. Gwarków 1, POLAND,


After the TENORM phenomenon had been considered thoroughly it turned out

that issues occur very frequently in our environment. It touches a lot of aspects of

our common life, starting from occupational risk at work places, trough some “con-

taminated” goods or even a visit in spa, and ending on huge amount of bulk waste

materials very often dumped in our vicinity. Each particular way of occurring of

TENORM determinates some unique scenario of exposition. Therefore there is

not a universal method for risk evaluation applicable for all possible situations.

Moreover, TENORM occurrence’s consequences can be assessed from different

points of view. Sometimes the public comprehension of TENORM is a plentiful

source of very serious effects far more detrimental and painful than direct exposi-

tion to radiation. Risk caused by TENORM is a subject where enforcing of ALARA

rule became very complex and multidimensional.

In this paper some proposal of TENORM’s classification and rules of its importan-

ce assessment from diverse points of view are described.

Page 184 of 199


TOWARDS A METHODOLOGY FORIDENTIFYING NON NUCLEAR SITES

WITH ENHANCED LEVELS OFRADIOACTIVITY

Christian Cosemans1), Hans Vanmarcke2)

1) ONDRAF / NIRAS, Avenue des Arts 14, B-1210 Brussels, BELGIUM2) SCK●CEN, Boeretang 200, B-2400 Mol, BELGIUM

The law of 12th December 1997 entrusts ONDRAF / NIRAS, among other things,

with the compilation of a repertory, detailing the location and status of all nuclear

sites and all sites containing radioactive substances on Belgian territory. This

repertory not only includes sites having a nuclear licence, but also non-nuclear

sites where enhanced levels of radioactivity occur due to the presence of natural

radiation sources. The identification of the nuclear sites is based on an inventory

of the nuclear licenses as they have been granted by the competent authorities.

As the non-nuclear sites do not require such license, their identification necessita-

tes a specific methodology.

This presentation outlines the methodology developed by ONDRAF/NIRAS and

SCK●CEN for identifying non-nuclear sites with enhanced levels of radioactivity.

The methodology combines data from an airborne radiometric survey of Belgium

and

a literature search in order to identify and locate the non-nuclear sites. This proves

Page 185 of 199


to be an extensive task undertaken by a taskforce combining the expertise of Con-

trolatom (Belgium), NRG (the Netherlands), ONDRAF / NIRAS and SCK●CEN.

Page 186 of 199


THE EFFECT OF EARTHQUAKE-INDUCEDRADON RELEASE ON THE POPULATION IN

THE SEISMIC ACTIVE REGIONS OF ARMENIA

E. Saghatelyan, A. Petrosyan, Yu. Aghbalyan, M. Baburyan,A. Davtyan

Armenian State Engineering University, 105 Teryan Str., 375009, The Center for

Ecological-Noosphere Studies of NAS RA, 68 Abovian Str., Yerevan, 375025,

ARMENIA


Page 187 of 199


For the first time on the basis of Spitak earthquake (Armenia, December 1988)

experience it is found out that the earthquake causes intensive and prolonged ra-

don splashes which, rapidly dispersing in the open space of close-to-earth at-

mosphere, are contrastingly displayed in covered premises (dwelling houses,

schools, kindergartens) even if they are at considerable distance from the epicen-

ter of the earthquake, and this multiplies the radiation influence on the population.

The interval of splashes includes the period starting from the first fore-shock and

ending by the last after-shock, i.e. several months. The area affected by radiation

is larger than the territory of Armenia. The scales of this impact on population is

12 times higher than the number of people injured in Spitak, Leninakan and other

settlements (toll of injured – 25 000 people, diseases caused by high levels of ra-

diation in non-adapted population – over 300 000). The radiations of the influence

are in direct correlation with the force of earthquake.

The basis for conclusion was the set of data on indoor radon monitoring in Yere-

van City beginning from 1987 (120 km from epicenter) 5450 measurements and

multivariate analysis with identification of cause-and-effect linkages between geo-

dynamics of indoor radon under stable and unstable conditions of Earth crust,

behavior of radon in different geological media during earthquakes, levels of room

radon concentrations and effective equivalent dose of radiation impact of ra-

diation dose on health and statistical information of the Ministry of Health on pu-

blic health, etc.

As we have discovered, calculations of equivalent radiation dose show that com-

pared with 1987, 1991 is character is by lower radon and its radio nuclides made

up about 16mSv, i.e. 50 times more than mean radon equivalent radiation dose of

the above-mentioned years. In the evidential part of the earthquake hearth the

level of background radiation in dwelling houses as well as radon effective ra-

diation dose radon, was many times higher. The interval of radon action is from

first foreshock to the last aftershock, i.e. several months.

The following facts which have not received explanation up till now can be consi-

dered as consequences of long-lasting radiation influence on human organism:

long-lasting state of apathy and indifference typical for the population of Armenia

during the period of more than a year after the earthquake, prevalence of mali-

Page 188 of 199


gnant cancer forms in disaster zones, prevalence of lungs cancer over the other

forms of oncology diseases, etc.

The danger of the influence of natural radiation provoked by the earthquake exists

for all urban territories of seism active regions, and it requires coordination of inve-

stigations in different countries according to precisely-elaborated programmers.

Page 189 of 199


210PO AND 210PB IN ENVIRONMENTALSAMPLES IN FINNISH LAPLAND

Dina Solatie, Kristina Rissanen

TUK-Radiation and Nuclear Safety Authority, Regional Laboratory in Northern

Finland, Research and Environmental Surveillance, Louhikkotie 28, 96500

Rovaniemi, FINLAND


210Po and 210Pb are members of the 238U decay chain. 210Po (T1/2 = 138 d) is formed

by the decay of 210Pb (T1/2 = 22 y) via 210Bi (T1/2 = 5 d). In the atmosphere 222Rn

formats its decay products 210Po and 210Pb which are deposited on the ground and

thus enter the human food-chain. In Finland most exposed are the Sami people

having substantial intakes of reindeer meat.

In the Regional Laboratory in Northern Finland, measurements of 210Po and 210Pb

activity concentrations in different environmental samples from Finnish Lapland

have been performed. Especially the arctic lichen-reindeer-man food chain has

been studied. The samples spiked with 208Po-tracer are leached by HNO3 and HCl.

After the solution is made slightly acid, ascorbic acid and hydrazine is added and

polonium is spontaneously deposited on nickel planchete. The 210Po-activity is

measured by -spectrometry. 210Pb is determined from the same solution about 6

moths later by carrying out another polonium deposition.

In this work plant and reindeer samples were collected early eighties and after

Chernobyl accident in the Finnish reindeer herding area. The results of 210Po andPage 190 of 199


210Pb activity concentrations and the ratio of 210Po / 210Pb in the plant and reindeer

samples are presented.

Page 191 of 199


NORM IN DRINKING WATER –MEASUREMENTS USING ULTRA LOW-LEVEL

LIQUID SCINTILLATION SPECTROMETRYAND CONSIDERATIONS FOR COMPLIANCEWITH THE EU DRINKING WATER DIRECTIVE

Franz Schönhofer1), Franz-Josef Maringer2)

1) Habicherg. 31/7, A-1160 Vienna, AUSTRIA, BEV – National Metrology

Institute, Arltgasse 35, A-1160 Vienna, AUSTRIA2) University of Natural Resources and Applied Life Science, Gregor Mendel-

Strasse 33, A-1180 Vienna, AUSTRIA

The European Union Directive on the Quality of Drinking Water requests member

states to control drinking water also for its radioactivity. The implications of the

Directive on the radiological survey of drinking water in Austrian will be discussed.

NORM usually causes the by far largest contribution to the population dose and

artificial radionuclides can in most circumstances be disregarded in drinking water.

A simple, time saving and cheap method has been developed, which allows for

simultaneous determination of 226Ra, 228Ra and 210Pb by using ultra low-level liquid

scintillation spectrometry. Also tritium and 222Rn (if required) can be easily

measured by LSC.

The Directive establishes a so-called "Indicative Dose": If the dose due to

ingestion of drinking water might exceed 0.1 mSv/y it should be considered,Page 192 of 199


whether the dose should be reduced by countermeasures. The requirements for

measurement methods and the strategy to determine compliance with the

Indicative Dose will be discussed.

Page 193 of 199


RADIUM IN GROUND WATER CLOSE TOBUENA LAGOON IN COASTAL ZONE OF RIO

DE JANEIRO STATE, BRAZIL

Dejanira C. Lauria1*, Rodrigo M. R. Almeida2, and Ondra Sracek3

1*Instituto de Radioproteção e Dosimetria (IRD), Rio de Janeiro, RJ, Brazil,; Fax:++552124422699

e-mail:[email protected]

2Department of Civil Engineering, Universidade Federal Fluminense (UFF), Rio

de Janeiro, RJ, Brazil3 Institute of Geological Sciences, Faculty of Science, Masaryk University,

Kotlářská 2, 611 37 Brno, Czech Republic

Ground water close to the head of Buena Lagoon has high salinity and low pH val-

ues. Radium is present predominantly as 228Ra. Factors responsible for high radi-

um mobility in ground water seem to be high salinity with resulting competition for

adsorption sites, and low pH values with resulting limited adsorption of Ra2+ on

positively charged surface of adsorbents. Behavior of uranium and thorium is also

influenced by their speciation and low pH conditions. Uranium is present as posi-

tively charged uranyl ion UO22+ in low pH samples and is very mobile. Similarly,

presence of positively charged Th4+ and thorium complexes with sulfate result in

relatively high thorium concentrations at low pH range. On the other hand, mobility

of phosphate released from dissolving monazite is probably reduced due to its ad-

sorption and precipitation close to its source.

Page 194 of 199


Keywords Groundwater, Coastal aquifer, Water geochemistry, Natural radioac-

tive isotopes, Rio de Janeiro

Page 195 of 199


IMPROVING CRITERIA FOR REMEDIATIONOF MONAZITE BY-PRODUCTS

CONTAMINATED SITES IN BRAZIL

Briquet, Claudia ; Silva, Katia, M.; Cipriani, M.

Comissão Nacional de Energia Nuclear/CNEN

Rua General Severiano, 90 Rio de Janeiro, Brasil

e-mail: [email protected] , [email protected] ,[email protected]

In 1999 the first Brazilian decommissioning process occurred in São Paulo State

at a monazite physical and chemical treatment plant, closed down since 1992.

The decommissioning process comprised equipment, piping, buildings and land

decontamination with the final site release for unrestricted use. At the present

time, another monazite site is being decommissioned in the same State. Regula-

tions for intervention situation in mining and milling of ores with uranium and tho-

rium associated are being developed now, due to this, the decommissioning activi-

ties have been based on case-by-case analysis and ALARA criteria. Investigations

are being made to propose suggestions for public participation in the process and

establish a method of working together, in order to obtain a more effective com-

munication between regulatory agency and society.

This paper presents an overview on the situation of three sites in São Paulo State:

a past and a present remediation case and a site to be decontaminated in the fu-

ture. All sites presented contamination with radioactive residues produced by out-

Page 196 of 199


dated monazite chemical processing. We also propose some proceedings im-

provement based on past experience and international guidelines. This paper

also suggest the implementation of public participation in the remediation process

evaluation.

Page 197 of 199


ENVIRONMENTAL ASSESSMENT OF THEMATERIAL DEPOSITED ON THE FORMER

URANIUM MINING DISPOSAL DUMP INRADONIÓW

A.Żak, M.Biernacka, K. Isajenko, P.Lipiński, K. Posłuszny

Central Laboratory for Radiological Protection

Konwaliowa St. 7, PL-03-194 Warszawa, Poland


T.J. Sibiga

MOSTOSTAL Warszawa SA

Konstruktorska St. 11A, PL-02-673 Warszawa, Poland

Radoniów is a small town located in Lubomierz district near Jelenia Góra (south-west part ofPoland). Beginning from the end of World War II up to the end of sixties there were uranium miningactivities in the vicinity of the town. Uranium deposits were almost entirely exploited and the tracesof the mining activities are the post-uranium dumps on the east side of mount Głębiec. The area ofthe terrain is about 6,85 ha. The material present on the dumps (containing high amount of ura-nium) is to be – according to the district authorities plans - used as the bedding for the constructionof the road around the town (PHARE contract).

The measurements performed by the Central Laboratory for Radiological Protection (CLOR)and ordered by MOSTOSTAL-Warszawa (developer of the road) were to asses the usability of thedumped material for road construction.

Page 198 of 199


The assessment program consisted of:

environmental measurements at the disposal site (dumps) of the uranium mine in

Radoniów;

assessment of the usability of the materials from the dumping site for the con-

struction of the circular road passing by Radoniów (part of the state road No. 30);

analysis of the risk for the workers having contact with the material deposited on

the dumps in Radoniów.

The following tasks were performed:

- measurement of the whole area by the mobile spectrometric laboratory (creating

the radiological map of the area);

- measurements of the beta radioactivity at the surface of the material disposed on

Radoniów dumps in 41 measurement points (RKP-1 radiometer);

- measurements of the gamma dose rate in 41points (RKP-1 radiometer);

- measurements of the gamma dose rate in 41points (Exploranium GR-130);

- measurements of the gamma dose rate in 5points (ionization chamber);

- measurement of the gamma spectra in 3 points on the dumps and 2 points rep-

resenting local background;

- sampling for further analysis in the laboratories of the CLOR (gamma spectrome-

try performed using natural radioactive contamination analyzers AZAR-90 and

MAZAR-95).

The following samples were taken:

- 41 samples of the surface material of the dump (10 cm depth);

- 10 samples from the deep layers of the dump (taken by the specialized geologi-

cal company “Geological Services”);

- 2 samples representing local natural environment.

Every sample of the surface material of the dump was averaged from the 5 to 7

points collected from the central point and the points situated in the distance of 2

meters from the center.

Detailed description of the measurement methods, the results and their in-

terpretation are presented in the poster.

Page 199 of 199

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